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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 Entergy 450 Broadway, GSB I RO. Box 249 Buchanan, NY 10511-0249 Tel 914 734 6700 Fred Dacimo Site Vice President Administration May 31, 2005 Indian Point Units 2 and 3 Docket Nos. 50-247, and 50-286 NL-05-070 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, Maryland 20852
SUBJECT:
Response to NRC Guidance for Use in Achieving Satisfactory Compliance With February 25, 2002 Order EA-02-026, Section B.5.b
REFERENCES:
- 1. March 18, 2002, Entergy Operations, Inc. - Response to Issuance of Order for Interim Safeguards and Security Compensatory Measures (NL-02-041 andlPN-02-016)
- 2. February 25, 2005 letter from J. E. Dyer to Holders of Licenses for Operating Power reactors as Listed in Enclosure 1 NRC Staff Guidance for Use in Achieving Satisfactory Compliance with February 25, 2002, Order Section B.5.b.
Dear Sir:
The NRC issued Order For Interim Safeguards and Security Compensatory Measures ("Order EA-02-026" or "ICM Order") dated February 25, 2002, for Indian Point Units 2 and 3.
Order EA-02-026 imposed requirements on nuclear power plants licensed pursuant to the Atomic Energy Act of 1954 and Title 10 of the Code of Federal Regulations.Section III.A of the Order required licensees to implement certain changes in physical security plans and safeguards contingency plans on an interim basis until final requirements were established. Among other requirements, Entergy Nuclear Operations, Inc. (ENO) completed implementation of the requirements of Section lI.B.5.b. of Order EA-02-026 by August 31, 2002.
Subsequently, the NRC issued Orders, dated April 29, 2003, Requiring Compliance with Revised Design Basis Threat for Operating Power Reactors ("Order EA-03-086" or 'DBT Order") and other security related Orders (collectively "Orders") for Indian Point Units 2 and 3. In many ways, Order EA-03-086 complemented or superseded requirements the interim measures imposed by Order EA-02-026.
As required by Order EA-03-086, the plans for the above-mentioned licensed facility have been implemented.
Subsequently, ENO was requested to respond to your letter dated February 25, 2005, NRC Staff Guidance for Use SAFEGUARDS INFORMATION Notice: Enclosure contains 'Safeguards Information."
Upon separation of the Enclosure, this letter and the Attachment are "Decontrolled."
'I'
Docket Nos. 50-247, and 50-286 NL-05-070 Page 2 of 3 InAchieving Satisfactory Compliance with February 25,2002, Order Section B.5.b, ("NRC B.5.b. Guidance") by May 31, 2005, and to implement appropriate enhancement to current mitigation strategies by August 31, 2005.
Specifically, nuclear power plant licensees were requested by Enclosure 2, Developing Mitigating Strategies /
Guidance for Nuclear Power Plants to Respond to Loss of Large Areas of the Plant in Accordance with B.5.b of the February 25, 2002, Order (dated February 24, 2005) (NRC B.5.b. Guidance"), to the February 25, 2005, letter to review the Areas of Consideration delineated in Attachment A to that Enclosure and evaluate additional considerations for potential inclusion in the licensees' mitigating strategies that licensees deemed appropriate in accordance to Attachment B to that Enclosure.
Subsequently, the Nuclear Energy Institute (NEI"), in conjunction with the NEI Security Working Group, developed and issued guidance for licensee use (CNEI Guidancel)to assist licensees in responding to the February 25, 2005, letter.
As requested in the February 25, 2005, letter, ENO has reviewed the information in Attachments A and B in accordance with the NEI Guidance and is hereby submitting, as a Safeguards Information enclosure to this letter (Enclosure), ENO's evaluation of the information the NRC provided. The Enclosure reflects the results of a comprehensive and thorough review of the guidance and describes the considerations that ENO either has already or intends to implement at Indian Point Units 2 and 3 by August 31, 2005.
The primary guiding principles used in the conduct of this evaluation were (1) whether or not equipment and resources were "readily available,' and (2) if equipment is readily available, can it be effectively utilized in a licensee's mitigating strategy. ENO considered "readily available to mean that the equipment or resources was already licensee owned, under contract, or part of an existing Memorandum of Understanding. Further, even if equipment and resources are readily available, the second criterion is to ensure that the equipment can be used in a mitigating strategy in an effective manner. Even if the equipment is readily available, it is of no value if it cannot be effective in implementing the mitigating strategy.
In accordance with these principles, mitigative strategies are being implemented to address the NRC B.5.b.
Guidance. These actions are considered to be commitments for that purpose and will be managed in accordance with ENO's commitment management system. The Attachment to this letter identifies those actions ENO considers commitments and the schedule that ENO has developed regarding the implementation of these commitments.
If you have any questions, or require additional information, please contact Mr. Patric W. Conroy, Manager, Licensing at (914) 736-6668 Sincerely, red R. Dacimo Site Vice President Indian Point Energy Center Attachment - Schedule for Completion of Actions and List of Regulatory Commitments Enclosure - ENO Evaluation of NRC B.5.b Guidance SAFEGUARDS INFORMATION Notice: Enclosure contains "Safeguards Information.
Upon separation of the Enclosure, this letter and the Attachment are "Decontrolled."
Docket Nos. 50-247, and 50-286 NL-05-070 Page 3 of 3 cc: w/ enclosure and attachment Mr. Samuel J. Collins Mr. Patrick D. Milano, Sr. Project Manager Regional Administrator-Region I Project Directorate I U.S. Nuclear Regulatory Commission Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission cc: w/o enclosure or attachment Mr. J. E. Dyer Resident Inspectors' Office Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Indian Point Unit 2 Assistant General Counsel for Materials Resident Inspectors' Office Litigation and Enforcement U.S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission Indian Point Unit 3 Mr. Michael K. Webb, Project Manager Mr. Peter Smith, President Project Directorate IV New York State Energy, Research, Division of Licensing Project Management and Development Authority Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Director Mr. Paul Eddy Office of Nuclear Materials and Safeguards NYS Department of Public Service U. S. Nuclear Regulatory Commission SAFEGUARDS INFORMATION Notice: Enclosure contains "Safeguards Information."
Upon separation of the Enclosure, this letter and the Attachment are Decontrolled."