Letter Sequence Supplement |
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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
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Text
Entergy Nuclear Northeast Entergy Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Robert Walpole Licensing Manager Tel 914 734 6710 January 4, 2011 NL-1 1-002 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Supplement to Response to Request for Additional Information on Relief Request RR-3-49 and RR-3-50 For Third Ten-Year Inservice Inspection Interval (TAC Nos. ME4234, ME4235)
Indian Point Unit Number 3 Docket No. 50-286 License No. DPR-64
REFERENCES:
- 1. Entergy Letter NL-10-061 Regarding 10 CFR 50.55a Relief Requests RR-3-49 and RR-3-50 from Examinations of Component Welds with Less Than Essentially 100 % Examination Coverage, dated July 5, 2010.
- 2. NRC Request for Additional Information on Indian Point 3 Relief Requests RR-3-49 and RR-3-50, ME4234, ME4235, dated October 28, 2010.
- 3. Entergy Letter NL-1 0-134 Regarding Request for Additional Information on Relief Request RR-3-49 and RR-3-50 For Third Ten-Year Inservice Inspection Interval (TAC Nos. ME4234, ME4235).
Dear Sir or Madam:
Entergy Nuclear Operations, Inc. (Entergy) submitted Relief Requests RR-3-49 and RR-3-50 for the Indian Point Unit No. 3 (IP3) Third Ten-Year Inservice Inspection Interval in Reference 1 and responded to a request for additional information (Reference 2) in Reference 3. The purpose of this letter is to provide a supplement to the information provided in Reference 3. This is provided based on further NRC clarification of a phone call to discuss the questions in Reference 2. The supplement to Reference 3 is found in Attachment 1.
NL-1 1-002 Docket No. 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.
Very truly yours, 4Az FbA).
RW/sp
Attachment:
- 1. Supplement to Response to Request for Additional Information Regarding Relief Requests RR-3-49 and RR-3-50 cc: Mr. John P. Boska, Senior Project Manager, NRC NRR DORL Mr. William M. Dean, Regional Administrator, NRC Region I NRC Resident Inspector's Office Indian Point Mr. Paul Eddy, New York State Department of Public Service
ATTACHMENT 1 TO NL-11-002 SUPPLEMENT TO RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS RR-3-49 AND RR-3-50 ENTERGY NUCLEAR 0101950041 PERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286
NL-1 1-002 Docket No. 50-286 Page 1 of 2 Attachment 1 Response to Request For Additional Information Regarding Relief Requests RR-3-49 and RR-3-50 By letter dated July 5, 2010, Agencywide Documents Access and Management System Accession No. ML101950041, Entergy Nuclear Operations, Inc. submitted an Indian Point Nuclear Generating Unit No. 3 (IP3) request to the Nuclear Regulatory Commission (NRC) for relief from the requirements of ASME Section Xl, Sub-article IWB-2500, Sub-article IWC-2500 and Code Case N-460, pursuant to 10 CFR 50.55a.
This was supplemented by letter dated December 8, 2010.
The NRC staff, in reviewing the submittal, requested additional information to complete its review. The NRC questions and the Entergy responses were previously addressed and the response to one question is being supplemented below.
RR-3-49 Question 1 For Examination Category R-A, Item Number AUGR, please address the following questions:
- 5. Fully clarify, in writing, the wave modality, insonification angles, coverage obtained for each beam direction for all ultrasonic (UT) examinations, and coverage calculations.
Supplement to Response Welds 1-4100-15, 1-4200-15, 1-4300-15, 1-4400-15 were inspected using 70 degree L, transducers. On the Reactor Vessel inlet nozzles, a cast stainless steel (A351 Grade CF8M) elbow is welded to the safe-end upstream of the dissimilar metal weld (welds 1-4100-15, 1-4200-15, 1-4300-15, 1-4400-15). There are currently no Appendix VIII (PDI) qualified procedures to inspect cast stainless steel materials. The entire volume was examined employing the Appendix VIII procedure qualified for the examination of austenitic welds. Examinations conducted using this procedure met or exceeded the required Appendix III examinations. Additionally, supplemental eddy current examinations were performed on these welds from the nozzle ID bore and detected no reportable indications.
The discussion below is to help describe the logic and methodology used in calculating the exam coverage estimates.
- 1. Code Required Examination Volume Code required examination volume that was scanned is estimated at greater than 96%.
This documents the code required examination volume that was scanned utilizing both a PDI qualified technique and the use of the PDI qualified procedure for areas where there is no PDI qualified procedures (i.e. the cast elbows). This coverage calculation considers all four required examination beam directions and shows that greater than
NL-1 1-002 Docket No. 50-286 Page 2 of 2 Attachment 1 96% of the code required examination volume was scanned on all 4 welds. The only limitations to scanning were due to ID surface condition configurations.
Weld 1-4100-15; 96.83% examined Weld 1-4200-15; 97.19% examined Weld 1-4300-15; 100% examined Weld 1-4400-15; 97.87% examined Calculation of limitations to circumferential scanning due to ID surface configurations were performed automatically in Paragon analysis software by use of the ultrasonically obtained ID profiles.
- 2. Examination Volume Coverage Credit When disallowing examination into or from the cast material, coverage of the code required volume is estimated at 45% (Figure 1 from Relief Request 49, ML101950041, is useful as an illustration). The limited coverage area includes any area which requires the sound to pass thru the cast stainless steel material. In the case of the axial scan from the cast side, this means no coverage is credited until the sound path travels from the transducer, thru the clad, directly into the weld, and then into the base metal of the safe-end. The same logic is applied for the axial scan from the safe-end side and the circ scans.
