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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARNL-18-063, Submission of IP2 Steam Generator Examination Program Results for the 2018 (2R23) Refueling Outage in Accordance with Technical Specification 5.6.72018-08-13013 August 2018 Submission of IP2 Steam Generator Examination Program Results for the 2018 (2R23) Refueling Outage in Accordance with Technical Specification 5.6.7 NL-18-049, 2018 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2018-07-10010 July 2018 2018 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements NL-18-021, Indian Point, Unit 2 - Submittal of Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Indian Point, Unit 2 - Submittal of Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-021, Submittal of Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Submittal of Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability ML18103A0302018-04-0606 April 2018 Attachment 1 to NL-18-021, LTR-SDA-18-035-NP, Revision 0, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-019, Relief Request Number IP2-ISI-RR-06 - Proposed Alternative to Use Reactor Vessel Head Penetration Flaw Weld Repair Method2018-04-0404 April 2018 Relief Request Number IP2-ISI-RR-06 - Proposed Alternative to Use Reactor Vessel Head Penetration Flaw Weld Repair Method NL-17-059, Request IP2-ISI-RR-22 for Relief from Examination of Non-Regenerative Heat Exchanger Base Support Welded Attachments for Fourth Ten-Year Inservice Inspection Interval Closeout2017-05-30030 May 2017 Request IP2-ISI-RR-22 for Relief from Examination of Non-Regenerative Heat Exchanger Base Support Welded Attachments for Fourth Ten-Year Inservice Inspection Interval Closeout NL-17-057, Request IP2-ISI-RR-20 for Relief from Examinations of Code Class 1 Component Welds with Less than Essentially 100% Examination Coverage for Fourth Ten-Year Inservice Inspection Interval Closeout2017-05-30030 May 2017 Request IP2-ISI-RR-20 for Relief from Examinations of Code Class 1 Component Welds with Less than Essentially 100% Examination Coverage for Fourth Ten-Year Inservice Inspection Interval Closeout NL-16-096, 2016 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2016-09-0909 September 2016 2016 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements NL-16-097, Fifth Ten Year Interval Inservice Inspection Program Plan2016-09-0606 September 2016 Fifth Ten Year Interval Inservice Inspection Program Plan NL-16-091, Submittal of Fifth Ten Year Interval Inservice Inspection Program Plan2016-08-17017 August 2016 Submittal of Fifth Ten Year Interval Inservice Inspection Program Plan NL-16-092, Submittal of Fifth Ten Year Interval Lnservice Testing Program Plan2016-08-17017 August 2016 Submittal of Fifth Ten Year Interval Lnservice Testing Program Plan NL-16-032, Entergy Transmittal of Indian Point 2 ASME Section XI, Iwl Concrete Containment Inspection in Accordance with the Parties Approved Settlement of License Renewal Contention NYS-24 Indian Point Unit 22016-03-16016 March 2016 Entergy Transmittal of Indian Point 2 ASME Section XI, Iwl Concrete Containment Inspection in Accordance with the Parties Approved Settlement of License Renewal Contention NYS-24 Indian Point Unit 2 NL-15-073, Request for Relief Request IP2-ISI-RR-18 Maintaining ISI Related Activities on the 2001 Edition/2003A ASME Section XI Code for Fifth 10-Year Inservice Inspection (ISI) Interval2015-06-0101 June 2015 Request for Relief Request IP2-ISI-RR-18 Maintaining ISI Related Activities on the 2001 Edition/2003A ASME Section XI Code for Fifth 10-Year Inservice Inspection (ISI) Interval NL-14-060, 2014 Summary Reports for In-Service Inspection and Repairs or Replacements2014-05-0909 May 2014 2014 Summary Reports for In-Service Inspection and Repairs or Replacements NL-13-032, Technical Specification 5.6.8 - IP3 Steam Generator Tube Inspection Report - Spring 2013 Refueling Outage2013-08-15015 August 2013 Technical Specification 5.6.8 - IP3 Steam Generator Tube Inspection Report - Spring 2013 Refueling Outage NL-13-031, Submittal of 2013 Summary Reports for Inservice Inspection and Repairs or Replacements2013-06-18018 June 2013 Submittal of 2013 Summary Reports for Inservice Inspection and Repairs or Replacements NL-13-040, Relief Request IP2-ISI-RR-16: Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination2013-02-20020 February 2013 Relief Request IP2-ISI-RR-16: Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination NL-13-002, Proposed Technical Specification Bases Changes to Credit Four Fan Cooler Units in Containment Integrity Analysis2013-01-28028 January 2013 Proposed Technical Specification Bases Changes to Credit Four Fan Cooler Units in Containment Integrity Analysis NL-11-075, Submittal of Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination2011-06-29029 June 2011 Submittal of Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination NL-11-050, Submittal of 2011 Summary Reports for In-Service Inspection and Repairs or Replacements2011-06-20020 June 2011 Submittal of 2011 Summary Reports for In-Service Inspection and Repairs or Replacements ML1024400362010-08-24024 August 2010 Submittal of Steam Generator Examination Program Results 2010 Refueling Outage (2R19) NL-10-058, Summary Reports for In-Service Inspection and Repairs or Replacements2010-06-0909 June 2010 Summary Reports for In-Service Inspection and Repairs or Replacements NL-10-059, Relief Request IP2-ISI-RR-11 for Fourth Ten-Year Inservice Inspection Interval2010-06-0303 June 2010 Relief Request IP2-ISI-RR-11 for Fourth Ten-Year Inservice Inspection Interval NL-09-107, Relief Request 2-10 for Fourth Ten-Year Inservice Inspection Interval2009-08-0505 August 2009 Relief Request 2-10 for Fourth Ten-Year Inservice Inspection Interval NL-09-097, Submittal of Fourth Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan2009-07-21021 July 2009 Submittal of Fourth Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan NL-09-090, Relief Requests 08 and 09 for Fourth Ten-Year Inservice Inspection Interval2009-07-0101 July 2009 Relief Requests 08 and 09 for Fourth Ten-Year Inservice Inspection Interval NL-09-069, 2009 Summary Reports for In-Service Inspection and Repairs or Replacements2009-07-0101 July 2009 2009 Summary Reports for In-Service Inspection and Repairs or Replacements NL-09-087, Relief Request IP3-ISI-RR-01, IP3-ISI-RR-02, and IP3-ISI-RR-03 for Fourth Ten-Year Inservice Inspection Interval2009-06-24024 June 2009 Relief Request IP3-ISI-RR-01, IP3-ISI-RR-02, and IP3-ISI-RR-03 for Fourth Ten-Year Inservice Inspection Interval NL-09-037, Response to Request for Information Regarding Request for Relief 3-48 Supporting Refuel Outage 15 Inservice Inspection Program2009-03-23023 March 2009 Response to Request for Information Regarding Request for Relief 3-48 Supporting Refuel Outage 15 Inservice Inspection Program NL-09-003, Supplemental Response to Request for Additional Information on Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination2009-01-20020 January 2009 Supplemental Response to Request for Additional Information on Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination NL-08-110, Summary Reports for In-Service Inspection and Repairs for Replacements2008-07-14014 July 2008 Summary Reports for In-Service Inspection and Repairs for Replacements NL-08-053, 10 CFR 50.55a Request RR-CRV-75 - Relief from Examinations of Component Welds with Less than Essentially 100% Examination Coverage for Third-Ten Year Inservice Inspection Interval Closeout2008-03-26026 March 2008 10 CFR 50.55a Request RR-CRV-75 - Relief from Examinations of Component Welds with Less than Essentially 100% Examination Coverage for Third-Ten Year Inservice Inspection Interval Closeout NL-07-069, Inservice Inspection Third Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval2007-06-13013 June 2007 Inservice Inspection Third Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval ML0707100072007-03-19019 March 2007 Summary of the Staff'S Review of the 2006 Steam Generator Tube Inservice Inspection Reports for Refueling Outrage 17 NL-07-028, Inservice Testing Program Summary for 4th Interval, Revision 02007-02-28028 February 2007 Inservice Testing Program Summary for 4th Interval, Revision 0 NL-07-029, 4th Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan2007-02-28028 February 2007 4th Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan NL-05-088, Inservice Inspection (ISI) Second Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval2005-07-0606 July 2005 Inservice Inspection (ISI) Second Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval NL-05-0211, Inservice Testing Program Summary for the Interval July 1, 1994 Through April 6.2006. Revision 32005-02-22022 February 2005 Inservice Testing Program Summary for the Interval July 1, 1994 Through April 6.2006. Revision 3 ML0506304052005-02-22022 February 2005 Inservice Inspection (ISI) Third Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval JPN-04-010, Request to Use 1998 Edition, 2000 Addenda of American Society of Mechanical Engineers (ASME) Section Xl Code Requirements for Examination of Reactor Vessel Closure Studs2004-04-14014 April 2004 Request to Use 1998 Edition, 2000 Addenda of American Society of Mechanical Engineers (ASME) Section Xl Code Requirements for Examination of Reactor Vessel Closure Studs NL-03-188, Request for Approval for Alternative to Use Code Case N-613-1 for Reactor Vessel Nozzle to Vessel Weld Inspection2003-12-30030 December 2003 Request for Approval for Alternative to Use Code Case N-613-1 for Reactor Vessel Nozzle to Vessel Weld Inspection NL-03-078, Relief Request RR 63, Risk-Informed Inservice Inspection (RI-ISI) Program2003-05-12012 May 2003 Relief Request RR 63, Risk-Informed Inservice Inspection (RI-ISI) Program NL-03-055, Withdrawal of Relief Request RR3-29 for Inservice Inspection Program2003-03-27027 March 2003 Withdrawal of Relief Request RR3-29 for Inservice Inspection Program NL-03-026, Refueling Outage Inservice Inspection (ISI) Program Summary Report - Third Outage, Second Period, Third Interval2003-02-25025 February 2003 Refueling Outage Inservice Inspection (ISI) Program Summary Report - Third Outage, Second Period, Third Interval NL-04-006, St Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval2003-01-20020 January 2003 St Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval ML0209900922002-04-0303 April 2002 Revised Relief Request Nos. 3-12, 3-14, 3-16 & 3-17, Third 10-Year Inservice Inspection Interval Program Plan ML0205803912002-02-0505 February 2002 Relief Request RR 3-28, Risk-Informed Inservice Inspection (RI-ISI) Program 2018-08-13
[Table view] 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
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Enterty Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 SPEntergy Buchanan, NY 10511-0249 Tel 914 734 6700 Robert Walpole Licensing Manager Tel (914) 734-6710 June 24, 2009 NL-09-087 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Relief Request IP3-ISI-RR-01, IP3-ISI-RR-02, and IP3-ISI-RR-03 For Fourth Ten-Year Inservice Inspection Interval Indian Point Unit Number 3 Docket No. 50-286 License No. DPR-64
Dear Sir or Madam:
Entergy Nuclear Operations, Inc. (Entergy) is submitting Relief Request IP3-1SI-RR-01 (Enclosure 1), Relief Request IP3-1SI-RR-02 (Enclosure 2), and Relief Request IP3-lSI-RR-03 (Enclosure 3),
for Indian Point Unit No. 3 (IP3). These relief requests are for the Fourth 10-year Inservice Inspection (ISI) Interval.
The enclosed relief requests evaluate the proposed alternatives and conclude they provide an acceptable level of quality and safety. The relief requests are requested under the provisions of 10CFR 50.55a(a)(3)(i).
Entergy requests approval of the relief requests within 12 months of docketing which will allow time for implementation during the next refuel outage.
zoq7 ljd-((
NL-09-087 Docket 50-286 Page 2 of 2 There are no new commitments identified in this submittal. If you have any questions or require additional information, please contact Mr. Robert Walpole, Licensing Manager at 914-734-6710.
Sincerely, RW/sp Enclosures 1. Relief Request No: IP3-1SI-RR-01 Proposed Alternative to Use ASME Code Case N-753
- 2. Relief Request No: IP3-1SI-RR-02 Proposed Alternative to Use Weld Reference System I
- 3. Relief Request No: IP3-ISI-RR-03 Proposed Alternative to Use ASME Code Case N-739-1 cc: Mr. John P. Boska, Senior Project Manager, NRC NRR DORL Mr. Samuel J. Collins, Regional Administrator, NRC Region 1 NRC Resident Inspector, IP3 Mr. Francis J. Murray, Jr., President and CEO, NYSERDA Mr. Paul Eddy, New York State Dept. of Public Service
Enclosure:
1 TO NL-09-087 RELIEF REQUEST NO: IP3-ISI-RR-01 PROPOSED ALTERNATIVE TO USE ASME CODE CASE N-753 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286
Indian Point Unit 3 Fourth 10-Year ISI Interval Relief Request No: IP3-ISI-RR-01 Revision 0 Page 1 of 2 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)
-Alternative Provides Acceptable Level of Quality and Safety-
- 1. ASME Code Component(s) Affected Code Class: Not Applicable
References:
ASME Section XI, 2001 Edition with 2003 Addenda, IWA-2321 (a)
Code Case N-753 Examination Category: Not Applicable Item Number: Not Applicable
==
Description:==
Alternative Requirements to the Visual Acuity Demonstration Requirements of IWA-2321 (a)
2. Applicable Code Edition and Addenda
The Code of Record for the Indian Point Unit 3 Inservice Inspection Fourth Interval is the ASME Section XI Code, 2001 Edition including the 2003 Addenda.
3. Applicable Code Requirement
IWA-2321(a) requires that NDE personnel be administered the following vision tests annually:
"Personnel shall demonstrate natural or corrected near-distance acuity of 20/25 or greater Snellen fraction, with at least one eye, by reading words or identifying characters on a-near-distance test chart, such as a Jaeger chart, that meets the requirements of IWA-2322. Equivalent measures of near-distance acuity may be used. In addition, personnel performing VT-2 or VT-3 visual examinations shall demonstrate natural or corrected far-distance acuity of 20/30 or greater Snellen fraction or equivalent with at least one eye."
4. Reason for Request
Pursuant to 10 CFR 50.55a(a)(3)(i), authorization is requested on the basis that the proposed alternative, use of Code Case N-753, would provide an acceptable level of quality and safety.
- 5. Proposed Alternative and Basis for Use Pursuant to 10 CFR 50.55a(a)(3)(i), Entergy requests authorization to utilize the alternative requirements in ASME Code Case N-753 in lieu of the requirements of IWA-2321 (a).
Relief Request No: IP3-1SI-RR-01 Page 2 of 2 Basis for Use Code Case N-753 provides an alternative to the visual acuity demonstration requirements of IWA-2321(a) that will allow the testing to be administered and documented by an Optometrist, Ophthalmologist, or other health care professional who administers vision tests.
The visual acuity testing for NDE personnel performing ASME Section XI examinations is required to be administered annually. In addition to this visual acuity testing, which is typically administered by utility personnel, many NDE personnel also have annual visual acuity testing in conjunction with routine eye examinations administered by an Optometrist, an Ophthalmologist, or other health care professional who administers vision tests.
Optometrists, Ophthalmologists, and other health'care professionals who administer vision tests are typically educated and experienced in the proper techniques for vision testing, such as the Snellen fraction or Jaeger-chart. methods required by ASME Section XI. This training and expertise provides a sound level of confidence that the Visual acuity testing administered will be a reliable indicator that the tested NDE personnel'.can satisfactorily perform Section XI non-destructive examinations.
The testing performed by Optometrists, Ophthalmologists, and other health care professionals who
-'administer Ivision tests will satisfy IWA-2321 (a) requirements, including documentation which details the tests performed, compliance with IWA-2321 (a) criteria and the date the testing was administered.-
The use of Code Case N-753 alternative requirements allows the flexibility for utilities to accept visual acuity testing performed by outside health care professional in lieu of the visual acuity testing performed by in-house personnel. In many instances this flexibility will eliminate duplicate testing and thus provide a reduction in-the costs and manpower associated with qualifying NDE personnel. ..
Because Code Case N-753 does not change the qualification criteria in IWA-2321 (ap), the implementation of the included alternative requirements does not affect the level of quality or safety provided by NDE personnel.
6.-Duration of Propo*Sed Alternative Rel*ief is rerq*'ested for the Fourth Ten Year Interval (effective from July 2009 thru July 2019).
- 7. Precedents This request is essentially identical to the previous Entergy South Request CEP-ISI-012 which was approved on. March 6, 2009 in TAC Nos. MD8813, MD8814, MD8815, and MD8816.
- 8. References -
None
Enclosure 2 TO. NL-09-087 RELIEF REQUEST NO: IP3--ISI-RR-02 .
PROPOSED ALTERNATIVE TO USE WELD REFERENCE SYSTEM ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286
Indian Point Unit 3
'Fourth 10-Year ISI Interval Relief Request No: IP3-ISI-RR-02 Revision 0 Page 1 of 3 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)
-Alternative Provides Acceptable Level of Quality and Safety-
- 1. ASME Code Component(s) Affected Code Class: 1 and 2
References:
2 -. " .-..-
.. IWA-2600 - -
Examination Category: Not Applicable Item Number: Not Applicable
Description:
Weld Reference System
2. Applicable Code Edition and Addenda
The Code of Record for the Indian Point Unit 3 (IP3) Inservice Inspection Fourth Interval is the ASME Section XI Code, 2001 Edition including the 2003 Addenda.
3. Applicable Code Requirement
Subarticle IWA-2600 requires the establishment of a weld reference system for all welds and areas subject to surface or volumetric examination. Each such weld area shall be located and identified by a system of reference points.
Appendix III, Subarticle 111-4300 requires the identification of examination areas. Weld identification and location shall be shown on a weld identification plan. Welds shall be marked once before or during the preservice examination to establish a reference point.
4. Reason for Request
IP3 requests relief from the requirements of the weld reference system as specified in IWA-2600 and 111-4300. Pursuant to 10 CFR 50.55a(a)(3)(i) authorization is requested on the basis that the proposed alternative would provide an acceptable level of quality and safety.
- 5. Proposed Alternative and Basis for Use The weld reference system described below shall be used for locating welds on existing piping and components and new installations.
Datum reference markings will be established in the event that recordable indications are to be reported. Such datum points shall either be marked on the component or have their locations adequately described in the inspection documentation so that subsequent relocation can be achieved.
Relief Request No: IP3-ISI-RR-02
. . . Page 2 of 3 The method proposed for the identification of indication locations is identical to the one employed at IP3 during thefirst; second, and third inspection intervals.
Basis for Use The current code requiremehts include the establishment of a weld reference system which includes the initial marking of weld joints. At the time of construction of.IP3, the application of a reference system which included the marking of welds before or during the preservice examination was not required by the code and, accordingly welds were not marked.
A reference system for controlling the selection and documentation of datum points has been in effect since preservice inspections were performed in the early 1970's. The datum and conventions established at that time have been retained to promote consistency in the recording of data. The
-;dgneral! cnventions 6Saat IP3 for establishing weld reference datum pointsinclude:
-Reference system for pipe:-
- The datum point for a circumferential weld on a horizontal pipe is the intersection of the top centerline of the pipe and the weld centerline. Dimensions are taken in a clockwise direction when viewing along the direction of system flow, which is marked on the line isometric drawing:
- The datum point for a circumferential weld on a vertical pipe is the intersection of the weld centerline and the centerline through the outside (extrados) of the elbow or bend that is'in the direction of the lowerweld number.---
- The datum for a longit-dinal weld is the weld centerline and the intersecting circumferential weld.
Reference system for vessels:
- The datum forcircumferential welds is the inters~ection-of the-weld centerline and the centerline of the adjacent longitudinal weld: Dimensions are taken in a clockwise direction when viewed from the top.
- Where there is no intersecting weld, the datum point is drawn from an existing structural point (e.g., the centerline of a hot leg manway). This-is identified on the
.
- datasheet for the weld examination.
- The datum for longitudinalwelds is the intersection of the weld centerline and the centerline of the intersecting upper circumferential Weld.
Relief Request No: IP3-ISI-RR-02 Page 3 of 3 The weld reference system currently in use at IP3 has been performing satisfactorily for the first, second,4 and third 10-Year Intervalsý The locations, of indications have been positively-identified using the-aforementioned conventions. Entergy believes the weld reference system currently in use at IP3 provides an acceptable level of safety and quality to address the requirements of
-Subsections IWA-2600 and 111-4300. Therefore, the marking of weld joints is not necessary.
- 6. Duration of Proposed Alternative- - - . -- -
Relief is. requested for the Fourth Ten Year Interval (effective from July 2009 thru July 2019).
- 7. Precedents This request is essentially identical to the previous Third 10-Year Inspection IntervalRelief 3-11 which was approved on 5/17/01 in TAc No. MA9757. -.. -
- 8. Referehces-""
Neon-<" . .- ',:*7 -- . - ... '* , , . -" °: ; . / '* "' -:. '- :* -:. ' . . ' -: ": .. ..
Enclosure 3 TO NL-09-087 RELIEF REQUEST NO: IP3-ISI-RR-03 PROPOSED ALTERNATIVE-TO. USE ASME CODE CASE.N-739-1 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286
Indian Point Unit 3 Fourth 10-Year ISI Interval Relief Request No: IP3-ISI-RR-03 Revision 0 Page 1 of 2 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)
-Alternative Provides Acceptable Level of Quality and Safety-
- 1. ASME Code Component(s) Affected. - -
Code Class:_:, -. .
References:
ASME Section Xl, 2001 Edition with 2003 Addenda, Article IWA-2300 and Subsection IWL-2310 Code Case N-739-1 Examination Category: L-A and L-B Item Number: 11.11, L1.12, L2.30
==
Description:==
Request to Utilize the Alternative Requirements of Code Case N-739-1: Alternative Qualification Requirements for Personnel Performing Class CC Concrete and Post-Tensioning System Visual Examinations'
2. Applicable Code Edition and Addenda
The Code of Record for the Indian Point Unit 3 Inservice Inspection Fourth Interval is the ASME Section X1 Code, 2001 Edition including the 2003 Addenda.
3. Applicable Code Requirement
IWA-2300 provides requirements for qualification of nondestructive, examination personnel.
IWL-2310 provides requirements for the qualification of personnel performing Class CC Concrete and Post-Tensioning System Visual Examinations.
Per 10 CFR 50.55a(b)(2)(viii)(F), personnel-that examine containment concrete surfaces and tendon hardware, wires, or strands must meet the qualification provisions in IWA-2300. The "owner-defined" personnel qualification provisions in IWL-2310(d) are not approved for use.
4. Reason for Request
Pursuant to 10 CFR 50.55a(a)(3)(i), authorization is requested on the basis that the proposed alternative, use of Code Case N-739-1, would provide an acceptable level of quality and safety.
- 5. Proposed Alternative and Basis for Use Pursuant to 10 CFR 50.55a(a)(3)(i), Entergy requests authorization to utilize the alternative
Relief Request No: IP3-ISI-RR-03 Page 2 of 2 requirements in ASME Code Case N-739-1 in lieu of the requirements of IWA-2300.
Basis for Use The reason the NRC has included the modificationr in-10CFR 5.55a(b)(2)(viii)(F), that prohibits licensees to utilize the "owner-defined" personnel qualification provisions in IWL-2310(d) is that they believe it is inappropriate to approve Code provisions that do not contain specific containment inspection guidance when prior experience demonstrates that specific containment inspection guidance is necessary. In lieu of the IWL-2310(d) personnel qualification requirements, the 10 CFR 5.55a(b)(2)(viii)(F) modification requires that licensees implement the IWA-2300 personnel qualification provisions.
In response to this NRC concern, ASME. has-developed an alternative set of qualification requirements in Code Case N-739-1. This Code Case provides detailed criteria to qualify personnel who examine containment concrete surfaces and tendon hardware, wires, or strands.
Similar to the requirements inJWA-2300, Code,:Case N-739-1 includes plant and Section -Xl:-'.,
Subsection IWL experience requirements. as.well as detajled!training proficiency requirements for.
personnel performing Class.CC concrete and, post-tensi*oning system yisualexaminations.
Entergy believes that the alternative requirements in Code*Case N-739-1 satisfy the NRC's concern of licensees utilizing Code requirements that do not contain specific containment
_i*inspection guidance., In,addition, Entergy believes that the alternative requirements in Code Case N-739-1 provide an acceptable level of quality and safety to the requirements in IWA-2300.
- 6. Duration of.Proposed Alternative ,.
_.--:._.-Relief_ is requestedfJortheFourth Ten Year Interval (effective from July 2009 thru July 2019).
- 7. Precedents This request is essentially identical to the previous Entergy South Request CEP-CISI-001Q which was approved in NRC letter dated March-30, 2009, ADAMS Accession Number ML090630469.
- 8. References None