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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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Entergy Nuclear Northeast Indian Point Energy Center 295 Broadway, Suite 1
- Entergy PO Box 249 Buchanan, NY 10511-0249 Tel 914 734 5340 Fax 914 734 5718 Fred Dacimno Vice President, Operations March 3, 2003 NL-03-037 Annette L. Vietti-Cook, Secretary Office of the Secretary of the Commission U. S. Nuclear Regulatory Commission Attn: Rulemakings and Adjudications Staff Washington, DC 20555-0001
SUBJECT:
Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Stations 2 and 3 Docket Nos. 50-247 and 50-286 Answer to February 11, 2003 Order to Modify PWR Licenses for Interim Inspection Requirements for Reactor Pressure Vessel Heads
References:
- 1. NRC letter dated February 11, 2003; S. Collins to Holders of Licenses for Operating Pressurized Water Reactors, "Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors."
- 2. Entergy letter to NRC, IPN-02-095; "Reactor Pressure Vessel Head and Penetration Nozzles Inspection Plan for Spring 2003 Refueling Outage,"
dated December 19, 2002.
Dear Ms. Vietti-Cook,
Pursuant to the requirements of 10 CFR 2.202(a)(2), Entergy Nuclear Operations, Inc (ENO) hereby submits for filing, in Attachment I, the answer to the NRC Order of February 11, 2003 regarding interim inspection requirements for reactor pressure vessel heads at pressurized water reactors. ENO consents to the Order modifying the licenses for Indian Point Unit 2 and Indian Point Unit 3. This response is being provided per the instructions stated in Section V of the Order.
ENO is currently planning to perform an inspection of the Indian Point 3 reactor pressure vessel head during the refueling outage (3R12) scheduled to begin March 28, 2003. The planned inspection, described in Reference 2, includes bare metal visual and, to the extent allowed by the outage schedule, NDE. Since the EDY (as defined in Section IV. A of the Order) for IP3 is in the moderate category for this outage, only one of these inspections is required to satisfy the conditions of the Order. However ENO is still planning to perform both inspections. This approach is desirable to obtain a baseline of data and to maintain the flexibility of performing either visual or
NL-03-037 Dockets 50-247 and 50-286 Page 2 of 3 NDE inspection if the EDY remains in the moderate category for the subsequent outage (3R13).
Therefore ENO is requesting the following relaxation pursuant to the procedure specified in Section IV.F of the Order.
Section IV.C (2)(b)(i) of the Order requires: "Ultrasonic testing of each RPV head penetration nozzle (i.e., nozzle base material) from two (2) inches above the J-groove weld to the bottom of the nozzle and ......
ENO can not comply with the requirement for ultrasonic testing 'to the bottom of the nozzle' because the penetration nozzles at Indian Point 3 are designed with a threaded region on the bottom 0.75 inches to accommodate the installation of guide funnels. Meaningful ultrasonic test data can not be obtained in this region. The ultrasonic testing will extend from two (2) inches above the J-groove weld to the top of the threaded region at the bottom of the penetration nozzle.
This coverage provides an acceptable level of quality and safety because it encompasses the weld heat affected zone, which is the area susceptible to primary water stress corrosion cracking.
In addition to the above relaxation request, ENO is providing a clarification regarding Footnote 1 of the Order, which identifies certain guidance to address flaw evaluations. ENO plans to use other guidance (EPRI MRP-44 and MRP-55) for flaw evaluations, as stated in Attachment I.
There are no new commitments identified by this letter. Should you have questions regarding this matter, please contact Mr. Kevin Kingsley at 914-734-5581.
V tuy urs, re .Dacimo Vice President, Operations Indian Point Energy Center Attachments:
- 1. Licensee's Answer to February 11, 2003 Commission Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors.
I1. Certificate of Service cc: next page
NL-03-037 Dockets 50-247 and 50-286 Page 3 of 3 cc:
Mr. Samuel J. Collins, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 05-E-07 Washington, DC 20555-0001 Mr. Hubert Miller Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Dennis C. Dambly Assistant General Counsel for Materials Litigation and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Mr. Pat Milano Senior Project Manager Division of Licensing Project Management Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop: O-8-C2 Washington, DC 20555-0001 Senior Resident Inspector Indian Point 2 Nuclear Power Plant U. S. Nuclear Regulatory Commission P. 0. Box 38 Buchanan, NY 10511 Resident Inspector's Office Indian Point 3 Nuclear Power Plant U. S. Nuclear Regulatory Commission P. 0. Box 337 Buchanan, NY 10511 Mr. Paul Eddy New York State Department of Public Service 3 Empire Plaza Albany, NY 12223
NL-03-037 Dockets 50-247 and 50-286 Attachment I Page 1 of 2 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
)
In the Matter of )
)
ENTERGY NUCLEAR OPERATIONS, INC. )
) Docket Nos. 50-247 and Indian Point Nuclear Generating Unit 2 and )
) 50-286 Indian Point Nuclear Generating Unit 3; )
) (EA-03-009)
LICENSEES' ANSWER TO FEBRUARY 11, 2003 COMMISSION ORDER ESTABLISHING INTERIM INSPECTION REQUIREMENTS FOR REACTOR VESSEL HEADS AT PRESSURIZED WATER REACTORS On February 11, 2003, the Nuclear Regulatory Commission ("NRC" or "Commission") issued an immediately effective order in the captioned matter entitled Order Modifying Licenses (Effective Immediately) ("Order") to, inter alia, Entergy Nuclear Operations, Inc. The Order stated that recent experience indicated that current inspection requirements in Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ("ASME Code") and related NRC regulations do not provide adequate assurance that reactor coolant pressure boundary integrity will be maintained for all combinations of construction materials, operating conditions, and operating histories at pressurized water reactors ("PWRs"). The Commission stated that long-term resolution of reactor pressure vessel ("RPV") head penetration inspection requirements is expected to involve changes to the ASME Code and NRC regulations, specifically 10 CFR 50.55a. Consequently, the Commission stated that it was necessary to establish a minimum set of RPV head inspection requirements, as a supplement to existing inspection and other requirements in the ASME Code and NRC regulations, through the issuance of the Order. Therefore, the Commission imposed interim inspection requirements set forth in Section IV of the Order pending the development of consensus standards and
NL-03-037 Dockets 50-247 and 50-286 Attachment I Page 2 of 2 incorporation of revised inspection requirements into 10 CFR 50.55a, directly or through reference to a future version of the ASME Code.
Pursuant to 10 CFR 2.202(d), Entergy Nuclear Operations, Inc. ("ENO") consents to the Order modifying the licenses for Indian Point Unit 2 and Indian Point Unit 3, as set forth in Section IV of the Order, and does not request a hearing in either of the dockets.
Footnote 1 of the Order cites a November 21, 2001, letter from J. Strosnider, NRC, to A. Marion, Nuclear Energy Institute, for guidance to address flaw evaluation. In lieu of the cited guidance, ENO intends to use the guidance in Electric Power Research Institute Report MRP-55, Revision 1, "Materials Reliability Program Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking ("PWSCC") of Thick-Wall Alloy 600 Materials", to evaluate PWSCC crack growth for the reactor vessel head penetration nozzle base metal comprising the inside surface and the portion of the outside surface protruding below the attachment J-groove weld.
Also, ENO intends to use the guidance in Electric Power Research Institute Report MRP-44, "PWR Materials Reliability Project Interim Alloy 600 Safety Assessments for US PWR Plants" (TP-1001491, Part 2, May 2001), to calculate the required ligament for circular cracks above the J-weld.
I declare under penalty of perjury that the foregoing is true and correct. Executed March 3, 2003.
Respectfully submitted, Ente uclear Operations, Inc.
re.Dacimo Vice President, Operations
I NL-03-037 Dockets 50-247 and 50-286 Attachment II Page 1 of 1 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of ))
ENTERGY NUCLEAR OPERATIONS, INC. )
) Docket Nos. 50-247 and Indian Point Nuclear Generating Unit 2, and )
) 50-286 Indian Point Nuclear Generating Unit 3 )
) (EA-03-009)
CERTIFICATE OF SERVICE I hereby certify under penalty of perjury that copies of the LICENSEES' ANSWER TO FEBRUARY 11, 2003 COMMISSION ORDER ESTABLISHING INTERIM INSPECTION REQUIREMENTS FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS in the captioned action have been served on the following by deposit in the United States mail and, in addition, by facsimile (indicated by an asterisk * ' ) as directed in Section V of the order, on this third day of March 2003.
- Annette L. Vietti-Cook, Secretary U. S. Nuclear Regulatory Commission Office of the Secretary ATTN: Document Control Desk U. S. Nuclear Regulatory Commission One White Flint North Attn: Rulemakings and Adjudications Staff 11555 Rockville Pike Washington, DC 20555-0001 Rockville, MD 20852-2738 Mr. Hubert Miller Mr. Samuel J. Collins, Director Regional Administrator, Region I Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission 475 Allendale Road Washington, DC 20555-0001 King of Prussia, PA 19406
- Assistant General Counsel for Materials Litigation and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Mr-.-ed R. Dacimo Vice President, Operations