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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 Roterty NucpleaNotes IndanaPontenegr Cne NYss051-024 Beuchaanr Robert Walpole Manager Regulatory Assurance NL-1 5-1 53 December 15, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
SUBJECT:
Commitment to Maintain Severe Accident Management Guidelines Indian Point Energy Center - Units 2 and 3 Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-6"4
Dear Sir or Madam:
The Nuclear Energy Institute (NEI) Nuclear Strategic Issues Advisory Committee (NSIAC) recently approved an Industry Initiative to implement and maintain Severe Accident Management Guidelines (SAMGs). This letter establishes commitments related to SAMGs for the Entergy Nuclear Operations, Inc. (Entergy) Indian Point Nuclear Generating Units No. 2 (1P2) and 3 (IP3).
These guidelines would be used by emergency response personnel during accident conditions that progress beyond the mitigation Capabilities described in Emergency Operating Procedures. SAMG strategies are intended to arrest the progression of fuel damage, maintain the capability of the containment as long as possible, and minimize radiological releases.
The new SAMG commitments for IP2 and IP3 are listed in the attachment.
It is expected that NRC staff personnel will conduct periodic inspection of the SAMGs and performance deficiencies, if any, will be assessed using the Reactor Oversight Process. It is also understood that inspection activities will not extend to Nuclear Regulatory Commission review and approval of SAMG strategies, or the use of equipment described in the SAMGs.
NL-15-153 Docket Nos. 50-247 and 50-286 Page 2 of 2 If you have any questions or require additional information, please contact me at (914) 254-6710.
Sincerely, RW/sp
Attachment:
List of Regulatory Commitments cc: Mr. Douglas Pickett, Senior Project Manager, NRC NRR DORL Daniel H. Dorman, Regional Administrator NRC Resident Inspector Mr. John B. Rhodes, President and CEO, NYSERDA Ms. Bridget Frymire, New York State Dept. of Public Service NRC Resident Inspectors Office
ATTACHMENT TO NL-1 5-1 53 LIST OF REGULATORY COMMITMENTS ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNITS NOS 2 AND 3 DOCKET NOS. 50-247 and 50-286
NL-15-153 Docket Nos. 50-247 and 50-286 Page 1 of 1 List of Regulatory Commitments Indian Point Nuclear Generating Units 2 and 3 TYPE (Check one) SCHEDULED ONE-TIME CONTINUING COMPLETION COMMITMENT ACTION COMPLIANCE DATE ENTERGY will consider the site Severe X October 31, 2016 Accident Management Guidelines (SAMGs) within plant configuration management processes in order to ensure that the SAMGs reflect changes to the facility over time.
SENTERGY will update the site Severe X Within two Accident Management Guidelines (SAMGs) refueling outages to future revisions of the Pressurized Water or three years of Reactor Owner's Group (PWROG) generic the publication severe accident technical guidelines, and date of the the SAMGs will be integrated with other guidelines, emergency response guideline sets and whichever is symptom-based Emergency Operating greater.
Procedures, and validated, using the guidance in NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents.
'~Entergy Roterty NucpleaNotes IndanaPontenegr Cne NYss051-024 Beuchaanr Robert Walpole Manager Regulatory Assurance NL-1 5-1 53 December 15, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
SUBJECT:
Commitment to Maintain Severe Accident Management Guidelines Indian Point Energy Center - Units 2 and 3 Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-6"4
Dear Sir or Madam:
The Nuclear Energy Institute (NEI) Nuclear Strategic Issues Advisory Committee (NSIAC) recently approved an Industry Initiative to implement and maintain Severe Accident Management Guidelines (SAMGs). This letter establishes commitments related to SAMGs for the Entergy Nuclear Operations, Inc. (Entergy) Indian Point Nuclear Generating Units No. 2 (1P2) and 3 (IP3).
These guidelines would be used by emergency response personnel during accident conditions that progress beyond the mitigation Capabilities described in Emergency Operating Procedures. SAMG strategies are intended to arrest the progression of fuel damage, maintain the capability of the containment as long as possible, and minimize radiological releases.
The new SAMG commitments for IP2 and IP3 are listed in the attachment.
It is expected that NRC staff personnel will conduct periodic inspection of the SAMGs and performance deficiencies, if any, will be assessed using the Reactor Oversight Process. It is also understood that inspection activities will not extend to Nuclear Regulatory Commission review and approval of SAMG strategies, or the use of equipment described in the SAMGs.
NL-15-153 Docket Nos. 50-247 and 50-286 Page 2 of 2 If you have any questions or require additional information, please contact me at (914) 254-6710.
Sincerely, RW/sp
Attachment:
List of Regulatory Commitments cc: Mr. Douglas Pickett, Senior Project Manager, NRC NRR DORL Daniel H. Dorman, Regional Administrator NRC Resident Inspector Mr. John B. Rhodes, President and CEO, NYSERDA Ms. Bridget Frymire, New York State Dept. of Public Service NRC Resident Inspectors Office
ATTACHMENT TO NL-1 5-1 53 LIST OF REGULATORY COMMITMENTS ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNITS NOS 2 AND 3 DOCKET NOS. 50-247 and 50-286
NL-15-153 Docket Nos. 50-247 and 50-286 Page 1 of 1 List of Regulatory Commitments Indian Point Nuclear Generating Units 2 and 3 TYPE (Check one) SCHEDULED ONE-TIME CONTINUING COMPLETION COMMITMENT ACTION COMPLIANCE DATE ENTERGY will consider the site Severe X October 31, 2016 Accident Management Guidelines (SAMGs) within plant configuration management processes in order to ensure that the SAMGs reflect changes to the facility over time.
SENTERGY will update the site Severe X Within two Accident Management Guidelines (SAMGs) refueling outages to future revisions of the Pressurized Water or three years of Reactor Owner's Group (PWROG) generic the publication severe accident technical guidelines, and date of the the SAMGs will be integrated with other guidelines, emergency response guideline sets and whichever is symptom-based Emergency Operating greater.
Procedures, and validated, using the guidance in NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents.
