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MONTHYEARML0307103082003-03-25025 March 2003 Environmental Assessment, Exemption from 10CFR50.44(F) for the Post Accident Containment Ventilation System Project stage: Approval ML0307103722003-04-0202 April 2003 Exemption Request, Post Accident Containment Ventilation System Project stage: Other 2003-03-25
[Table View] |
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Category:Exemption from NRC Requirements
MONTHYEARML23100A1262023-11-16016 November 2023 Enclosure 2 - Indian Point Energy Center Generating Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement ML23100A1442023-11-14014 November 2023 Enclosure 1 - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286) ML23063A1432023-11-0101 November 2023 Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML22228A2272022-08-12012 August 2022 FEMA Letter to NRC: Proposed Commission Paper Language for the Indian Point Nuclear Generating Unit Nos. 1, 2, and 3 Emergency Planning Decommissioning Exemption Request ML22208A0292022-07-19019 July 2022 E-Mail Transmitting Indian Point Exemption Draft EA ML22083A1912022-03-24024 March 2022 Request for Exemption from an Allowable Contents Requirement Contained in the Certificate of Compliance No. 1014 for the HI-STORM 100S Version E Cask ML22033A3482022-02-0101 February 2022 Revision to Holtec Decommissioning International, LLC (HDI Request for Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and 10 CFR Part 50, Appendix E for Indian Point Unit Nos. 1, 2, and 3 ML21356B6932021-12-22022 December 2021 Request for Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and 10 CFR Part 50, Appendix E ML20321A1212020-12-14014 December 2020 Exemption from Annual Force-on-Force Exercise Requirement of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Subsection VI.C.3(I)(1) (EPID L-2020-LLE-0189 (COVID-19)) ML20320A0002020-12-0808 December 2020 Temporary Exemption from Exercise Frequency Requirements of 10 CFR Part 50, Appendix E, Sections IV.F.2.B (EPID L-2020-LLE-0160 (COVID-19)) ML20309A7852020-11-23023 November 2020 Federal Register Notice for Exemption from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) for Holtec Decommissioning International, LLC ML20309A5772020-11-23023 November 2020 Letter with Exemption from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) for Holtec Decommissioning International, LLC ML20309A7812020-11-23023 November 2020 Exemption from 10 CFR 50.82 and 10 CFR 50.75 ML20316A0082020-11-10010 November 2020 Letter from A. Peterson (NYSERDA) to R. Guzman (Nrc), New York State Comments Indian Point Decommissioning Trust Fund Exemption Request ML20274A0012020-11-0505 November 2020 Federal Register Notice: Environmental Assessment and Finding of No Significant Impact and Exemption ML20236K1302020-09-29029 September 2020 Federal Register Notice Partial Exemption from Record Retention Requirements ML20236K0002020-09-28028 September 2020 Partial Exemption from Record Retention Requirements of 10 CFR 50.71(c); 10 CFR 50.59(d)(3); and 10 CFR Part 50, Appendix B ML20177A6452020-07-15015 July 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for June 2020 ML20156A0572020-06-12012 June 2020 Exemption Request from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Section VI (EPID L-2020-LLE-0050 (COVID-19)) ML20109A0032020-04-22022 April 2020 FRN - Indian Point Nuclear Generating Unit Nos. 2 and 3 - Exemption from the Requirements of 10 CFR Part 50, Appendix R, Section Iii.H, Related to Fire Brigade Annual Physical Examinations ML20109A0012020-04-22022 April 2020 Transmittal Letter with Exemption from the Requirements of 10 CFR Part 50, Appendix R, Section Iii.H, Related to Fire Brigade Annual Physical Examinations ML20109A0022020-04-22022 April 2020 Exemption from the Requirements of 10 CFR Part 50, Appendix R, Section Iii.H, Related to Fire Brigade Annual Physical Examinations ML20013D4952020-02-28028 February 2020 Letter - Indian Point Nuclear Generation Unit Nos. 2 and 3 - Exemption from the Requirements of 10 CFR 73.55 Related to the Suspension of Security Measures in an Emergency or During Severe Weather ML20013D5872020-02-28028 February 2020 Exemption from the Requirements of 10 CFR 73.55 Related to the Suspension of Security Measures in an Emergency or During Severe Weather ML20043C5392020-02-12012 February 2020 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) 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 ML1121405092012-02-0101 February 2012 Exemption from the Requirements of 10 CFR 50, Appendix R, Paragraph III.G.2 ML1121405302012-02-0101 February 2012 Exemption--Indian Point Nuclear Generating Unit No. 2 - Exemption from the Requirements of 10 CFR 50, Appendix R, Paragraph III.G.2 NL-09-031, Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions2009-03-0606 March 2009 Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions NL-09-032, Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions2009-03-0606 March 2009 Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions ML0724102542007-09-28028 September 2007 Exemption from the Requirements of 10 CFR Part 50, Appendix R ML0333608892003-12-0202 December 2003 Exemption from the Requirements of 10 CFR Part 50, Section 50.60(a) ML0307103722003-04-0202 April 2003 Exemption Request, Post Accident Containment Ventilation System ML0225505592002-09-12012 September 2002 Exemption from Requirements of 10 CFR Part 20, Section 20.1003 Definition of Total Effective Dose Equivalent (TEDE) 2023-11-16
[Table view] Category:Federal Register Notice
MONTHYEARML22313A0952022-12-0101 December 2022 Staffing Technical Specification License Amendment Federal Register Notice ML22313A0102022-12-0101 December 2022 Cyber Security License Amendment Federal Register Notice ML22217A0152022-11-0909 November 2022 FRN: Holtec Decommissioning International, LLC, Indian Point Energy Center, Independent Spent Fuel Storage Installation ML22215A0992022-10-26026 October 2022 Environmental Assessment and Finding of No Significant Impact Federal Register Notice ML21356B4982022-02-14014 February 2022 FRN - Indian Point Exemption Request 10 CFR Part 20 Appendix G ML21356B4972022-02-14014 February 2022 Enclosure - Indian Point Exemption Request 10 CFR Part 20 Appendix G ML21181A0282021-07-12012 July 2021 Individual Federal Register Notice, Notification of Public Meeting for Public Comments on Post-Shutdown Decommissioning Activities Report ML21162A0022021-06-15015 June 2021 Individual Federal Register Notice, Notification of the Availability of the Post-Shutdown Decommissioning Activities Report ML21162A0012021-06-15015 June 2021 Transmittal Letter, Notification of the Availability of the Post-Shutdown Decommissioning Activities Report in the Federal Register ML20309A7812020-11-23023 November 2020 Exemption from 10 CFR 50.82 and 10 CFR 50.75 ML20297A3602020-11-23023 November 2020 Federal Register Notice for Order Approving Transfer of Facility Operating Licenses to Holtec International, Owner, and Holtec Decommissioning International, LLC, Operator ML20309A7852020-11-23023 November 2020 Federal Register Notice for Exemption from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) for Holtec Decommissioning International, LLC ML20274A0002020-11-0505 November 2020 Letter with Environmental Assessment and Finding of No Significant Impact Use of Decommissioning Trust Funds for Spent Fuel Management and Site Restoration ML20274A0012020-11-0505 November 2020 Federal Register Notice: Environmental Assessment and Finding of No Significant Impact and Exemption ML20236K1302020-09-29029 September 2020 Federal Register Notice Partial Exemption from Record Retention Requirements ML20177A6452020-07-15015 July 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for June 2020 ML20109A0032020-04-22022 April 2020 FRN - Indian Point Nuclear Generating Unit Nos. 2 and 3 - Exemption from the Requirements of 10 CFR Part 50, Appendix R, Section Iii.H, Related to Fire Brigade Annual Physical Examinations ML20024F0532020-02-13013 February 2020 Extension of Comment Period Consideration of Approval of Transfer of Control of Licenses and Conforming Amendments ML20024F0632020-02-11011 February 2020 Extension of Comment Period for Notice of Consideration of Approval of Transfer of Control of Licenses and Conforming Amendments and Opportunity for a Hearing ML20006E1222020-01-15015 January 2020 Individual Federal Register Notice for Consideration of Approval of Transfer of Licenses and Conforming Amendments ML20003D0892020-01-13013 January 2020 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing ML20003D0882020-01-13013 January 2020 Letter with Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing ML19085A2172019-03-29029 March 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 04/09/2019 ML18211A5782018-09-17017 September 2018 Federal Register Notice - Announcing the Issuance of the Indian Point Renewed Licenses ML18096B3972018-05-16016 May 2018 Federal Register Notice for Issuance of Supplement 2 to the Indian Point Final Environmental Impact Statement for License Renewal NRC-2017-0238, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 20182017-12-21021 December 2017 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018 ML17353A1922017-12-21021 December 2017 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018 ML17065A0292017-04-13013 April 2017 OEDO-16-00411: Federal Register Notice Final Director'S Decision Under 10 CFR 2.206 NRC-2017-0074, OEDO-16-00411: Federal Register Notice Final Director'S Decision Under 10 CFR 2.2062017-04-13013 April 2017 OEDO-16-00411: Federal Register Notice Final Director'S Decision Under 10 CFR 2.206 ML16336A5002017-01-27027 January 2017 Federal Register Notice of Issuance of Order for Mta Transfer of Indian Pt 3 and FitzPatrick to Entergy Nuclear Operations, Inc. NRC-2017-0015, Federal Register Notice of Issuance of Order for Mta Transfer of Indian Pt 3 and FitzPatrick to Entergy Nuclear Operations, Inc. (CAC Nos. MF8286 and MF8287)2017-01-27027 January 2017 Federal Register Notice of Issuance of Order for Mta Transfer of Indian Pt 3 and FitzPatrick to Entergy Nuclear Operations, Inc. (CAC Nos. MF8286 and MF8287) NRC-2016-0202, Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 20162016-09-19019 September 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 2016 ML16257A5172016-09-19019 September 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 2016 ML16231A1402016-09-0707 September 2016 OEDO-16-00411: Acknowledgement Letter for Petitioner Lochbaum Concerning the Reactor Vessel Baffle-Former Bolt Degradation Identified During the Spring 2016 Refueling Outage at Indian Point Nuclear Generating Unit 2 NRC-2016-0197, OEDO-16-00411: Federal Register Notice Regarding 10 CFR 2.206 Petition for Indian Point Nuclear Generating, Unit No. 22016-09-0707 September 2016 OEDO-16-00411: Federal Register Notice Regarding 10 CFR 2.206 Petition for Indian Point Nuclear Generating, Unit No. 2 ML16231A1442016-09-0707 September 2016 OEDO-16-00411: Federal Register Notice Regarding 10 CFR 2.206 Petition for Indian Point Nuclear Generating, Unit No. 2 ML16119A4662016-04-28028 April 2016 Federal Register Notice: 05/04/16 - Short Notice ML16061A3012016-03-0202 March 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: March 15, 2016 ML16004A1182016-01-0707 January 2016 FRN, Issuance of Confirmatory Orders, Authorize Use of Preemption Authority Granted Under Provisions of Section 161A of the Atomic Energy Act of 1954, as Amended ML15329A0822015-12-21021 December 2015 FRN, Notice of Availability of Draft Supplement to Supplement 38 to the GEIS ML15320A2722015-12-0808 December 2015 Final Environmental Assessment and Finding of No Significant Impact Related to Preemption Authority Requests ML15320A2762015-12-0808 December 2015 Final Environmental Assessment and Finding of No Significant Impact Related to Preemption Authority Requests NRC-2015-0246, Final Environmental Assessment and Finding of No Significant Impact Related to Preemption Authority Requests2015-12-0808 December 2015 Final Environmental Assessment and Finding of No Significant Impact Related to Preemption Authority Requests ML15182A0152015-10-22022 October 2015 Draft Environmental Assessment and Finding of No Significant Impact Related to Preemption Authority Requests (CAC Nos. MF2603 - MF2605 and MF2637 - MF2639) ML15182A0172015-10-22022 October 2015 Draft Environmental Assessment (TAC Nos. MF2603-MF2605 and MF2637 - MF2639) ML15204A2792015-07-27027 July 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 4, 2015 ML15190A0362015-07-22022 July 2015 Federal Register Notice Withdrawal of an Amendment Request ML15148A3762015-06-0101 June 2015 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Published June 9, 2015 NRC-2015-0123, Application and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for2015-05-20020 May 2015 Application and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Acce ML15125A4952015-05-20020 May 2015 Application and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Acce 2022-02-14
[Table view] Category:Letter
MONTHYEARIR 05000003/20240022024-08-0606 August 2024 NRC Inspection Report 05000003/2024002, 05000247/2024002, 05000286/2024002 ML24171A0122024-06-18018 June 2024 Reply to a Notice of Violation EA-24-037 ML24156A1162024-06-0404 June 2024 Correction - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000003/20240052024-05-21021 May 2024 and 3 - NRC Inspection Report Nos. 05000003/2024005, 05000247/2024005, 05000286/2024005, 07200051/2024001, and Notice of Violation ML24128A0632024-05-0707 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024 HDI Annual Occupational Radiation Exposure Data Reports - 2023 ML24116A2412024-04-25025 April 2024 Annual Environmental Protection Plan Report ML24114A2282024-04-23023 April 2024 Annual Radioactive Effluent Release Report L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI) IR 05000003/20240012024-03-20020 March 2024 NRC Inspection Report Nos. 05000003/2024001, 05000247/2024001, and 05000286/2024001 (Cover Letter Only) ML24080A1722024-03-20020 March 2024 Reply to a Notice of Violation EA-2024-010 ML24045A0882024-02-22022 February 2024 Correction to the Technical Specifications to Reflect Appropriate Pages Removed and Retained by Previous License Amendments ML24053A0642024-02-22022 February 2024 2023 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report ML24011A1982024-01-12012 January 2024 ISFSI, Notice of Organization Change for Site Vice President ML23342A1082024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan ML23353A1742023-12-19019 December 2023 ISFSI, Emergency Plan, Revision 23-04 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan ML23338A2262023-12-0404 December 2023 Signed Amendment No. 27 to Indemnity Agreement No. B-19 ML23356A0212023-12-0101 December 2023 American Nuclear Insurers, Secondary Financial Protection (SFP) Program ML23242A2772023-11-30030 November 2023 NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML23338A0482023-11-30030 November 2023 ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28 ML22339A1572023-11-27027 November 2023 Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E IR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML23100A1252023-11-17017 November 2023 Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement ML23050A0032023-11-17017 November 2023 Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage ML23100A1432023-11-16016 November 2023 Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286) L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23064A0002023-11-13013 November 2023 NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) ML23063A1432023-11-0101 November 2023 Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23292A0262023-10-19019 October 2023 LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit ML23270A0082023-09-27027 September 2023 Registration of Spent Fuel Casks ML23237A5712023-09-22022 September 2023 09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23242A2182023-09-12012 September 2023 IPEC NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286) ML23250A0812023-09-0707 September 2023 Registration of Spent Fuel Casks ML23255A0142023-08-31031 August 2023 LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 ML23227A1852023-08-15015 August 2023 Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme ML23222A1442023-08-10010 August 2023 Registration of Spent Fuel Casks ML23208A1642023-07-26026 July 2023 Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater ML23200A0422023-07-19019 July 2023 Registration of Spent Fuel Casks ML23235A0602023-07-17017 July 2023 LTR-23-0194 Dwaine Perry, Chief, Ramapo Munsee Nation, Ltr Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23192A1002023-07-11011 July 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme 2024-08-06
[Table view] |
Text
April 2, 2003 Mr. Michael Kansler Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 - EXEMPTION FROM THE REQUIREMENTS OF 10 CFR PART 50, SECTION 50.44(f)
(TAC NO. MB6484)
Dear Mr. Kansler:
The Commission has approved the enclosed exemption from specific requirements of Title 10 of the Code of Federal Regulations, Part 50, Section 50.44(f), for the Indian Point Nuclear Generating Unit No. 3. This action is in response to your letter of October 3, 2002, as supplemented by letters dated January 16 and March 11, 2003, that submitted a proposed exemption that would eliminate the licensing basis requirements for the post accident containment ventilation system.
A copy of the exemption has been forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Patrick Milano, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-286
Enclosure:
Exemption cc w/encl: See next page
April 2, 2003 Mr. Michael Kansler Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 - EXEMPTION FROM THE REQUIREMENTS OF 10 CFR PART 50, SECTION 50.44(f)
(TAC NO. MB6484)
Dear Mr. Kansler:
The Commission has approved the enclosed exemption from specific requirements of Title 10 of the Code of Federal Regulations, Part 50, Section 50.44(f), for the Indian Point Nuclear Generating Unit No. 3. This action is in response to your letter of October 3, 2002, as supplemented by letters dated January 16 and March 11, 2003, that submitted a proposed exemption that would eliminate the licensing basis requirements for the post accident containment ventilation system.
A copy of the exemption has been forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Patrick Milano, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-286
Enclosure:
Exemption cc w/encl: See next page DISTRIBUTION:
PUBLIC R. Laufer W. Beckner B. Platchek, RI PDI R/F R. Pulsifer P. Milano OGC J. Zwolinski D. Cullison S. Little ACRS S. Richards T. McGinty, EDO G. Hill (2)
Accession Number: ML030710372 *See previous concurrence OFFICE PDI-2\PM PDI-1\PM PDI-1\LA RLEP* RTSB* SPLB*
NAME RPulsifer PMilano CRaynor for SLittle JTappert RDennig SWeerakkody DATE 04/01/03 04/01/03 04/01/03 03/17/03 03/17/03 03/14/03 OFFICE OGC PDI-1\SC PDI\D DLPM\D NAME SCole RLaufer SRichards JZwolinski DATE 04/01/03 04/02/03 04/02/03 04/02/03 OFFICIAL RECORD COPY
Indian Point Nuclear Generating Unit No. 3 cc:
Mr. Jerry Yelverton Mr. Harry P. Salmon, Jr.
Chief Executive Officer Director of Oversight Entergy Operations Entergy Nuclear Operations, Inc.
1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. Robert J. Barrett Mr. James Comiotes Vice President - Operations Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 3 Indian Point Nuclear Generating Unit 3 295 Broadway, Suite 3 295 Broadway, Suite 3 P. O. Box 308 P.O. Box 308 Buchanan, NY 10511-0308 Buchanan, NY 10511-0308 Mr. Dan Pace Mr. John McCann Vice President Engineering Manager, Licensing and Regulatory Affairs Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
440 Hamilton Avenue Indian Point Nuclear Generating Unit 2 White Plains, NY 10601 295 Broadway, Suite 1 P. O. Box 249 Mr. James Knubel Buchanan, NY 10511-0249 Vice President Operations Support Entergy Nuclear Operations, Inc. Resident Inspectors Office 440 Hamilton Avenue U.S. Nuclear Regulatory Commission White Plains, NY 10601 295 Broadway, Suite 3 P.O. Box 337 Mr. Joseph DeRoy Buchanan, NY 10511-0337 General Manager Operations Entergy Nuclear Operations, Inc. Regional Administrator, Region I Indian Point Nuclear Generating Unit 3 U.S. Nuclear Regulatory Commission 295 Broadway, Suite 3 475 Allendale Road P. O. Box 308 King of Prussia, PA 19406 Buchanan, NY 10511-0308 Mr. John M. Fulton Mr. John Kelly Assistant General Counsel Director - Licensing Entergy Nuclear Operations, Inc.
Entergy Nuclear Operations, Inc. 440 Hamilton Avenue 440 Hamilton Avenue White Plains, NY 10601 White Plains, NY 10601 Ms. Stacey Lousteau Ms. Charlene Faison Treasury Department Licensing Entergy Services, Inc.
Entergy Nuclear Operations, Inc. 639 Loyola Avenue 440 Hamilton Avenue Mail Stop: L-ENT-15E White Plains, NY 10601 New Orleans, LA 70113
Indian Point Nuclear Generating Unit No. 3 cc:
Mr. William M. Flynn, President Mr. Ronald Schwartz New York State Energy, Research, and SRC Consultant Development Authority 64 Walnut Drive 17 Columbia Circle Spring Lake Heights, NJ 07762 Albany, NY 12203-6399 Mr. Ronald J. Toole Mr. J. Spath, Program Director SRC Consultant New York State Energy, Research, and Toole Insight Development Authority 605 West Horner Street 17 Columbia Circle Ebensburg, PA 15931 Albany, NY 12203-6399 Mr. Charles W. Hehl Mr. Paul Eddy SRC Consultant Electric Division Charles Hehl, Inc.
New York State Department 1486 Matthew Lane of Public Service Pottstown, PA 19465 3 Empire State Plaza, 10th Floor Albany, NY 12223 Mr. Alex Matthiessen Executive Director Mr. Charles Donaldson, Esquire Riverkeeper, Inc.
Assistant Attorney General 25 Wing & Wing New York Department of Law Garrison, NY 10524 120 Broadway New York, NY 10271 Mr. Paul Leventhal The Nuclear Control Institute Mayor, Village of Buchanan 1000 Connecticut Avenue NW 236 Tate Avenue Suite 410 Buchanan, NY 10511 Washington, DC, 20036 Mr. Ray Albanese Mr. Karl Copeland Executive Chair Pace Environmental Litigation Clinic Four County Nuclear Safety Committee 78 No. Broadway Westchester County Fire Training Center White Plains, NY 10603 4 Dana Road Valhalla, NY 10592 Jim Riccio Greenpeace 702 H Street, NW Suite 300 Washington, DC 20001
7590-01-P UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286 EXEMPTION
1.0 BACKGROUND
Entergy Nuclear Operations, Inc., (ENO or the licensee) is the holder of Facility Operating License No. DPR-64 which authorizes operation of the Indian Point Nuclear Generating Unit No. 3 (IP3). The license provides, among other things, that the facility is subject to all rules, regulations, and orders of the U.S. Nuclear Regulatory Commission (NRC, the Commission) now or hereafter in effect.
The facility consists of a pressurized-water reactor located in Westchester County in the State of New York.
2.0 REQUEST/ACTION Title 10 of the Code of Federal Regulations (10 CFR), Part 50.44, Standards for combustible gas control system in light-water-cooled power reactors, requires that each pressurized light-water nuclear power reactor fueled with oxide pellets within cylindrical zircaloy or ZIRLO cladding must be provided with the capability for controlling the combustible gas concentrations in the containment following a postulated loss-of-coolant accident (LOCA). A combustible gas control system is defined by 10 CFR 50.44(h) as a system that operates after a LOCA to maintain the concentrations of combustible gases within the containment, such as hydrogen, below flammability limits. Combustible gas control systems are of two types:
(1) systems that allow controlled release from containment such as a purge or vent system, and (2) systems that do not result in a significant release from containment such as hydrogen recombiners. The combustible gas control system at IP3 consists of a hydrogen recombiner system and a backup purge system.
When IP3 was initially licensed, the post accident containment ventilation (PACV) system was installed to meet the requirements of 10 CFR 50.44(f). Section 50.44(f) requires:
For facilities with respect to which the notice of hearing on the application for a construction permit was published between December 22, 1968, and November 5, 1970, if the incremental radiation dose from purging (and repressurization if a repressurization system is provided) occurring at all points beyond the exclusion area boundary after a postulated LOCA calculated in accordance with §100.11(a)(2) of this chapter is less than 2.5 rem to the whole body and less than 30 rem to the thyroid, and if the combined radiation dose at the low population zone outer boundary from purging and the postulated LOCA calculated in accordance with §100.11(a)(2) of this chapter is less than 25 rem to the whole body and less than 300 rem to the thyroid, only a purging system is necessary, provided that the purging system and any filtration system associated with it are designed to conform with the general requirements of Criteria 41, 42, and 43 of appendix A to this part. Otherwise the facility shall be provided with another type of combustible gas control system (a repressurization system is acceptable) designed to conform with the general requirements of Criteria 41, 42, and 43 of appendix A to this part. If a purge system is used as part of the repressurization system, the purge system shall be designed to conform with the general requirements of Criteria 41, 42, and 43 of appendix A to this part. The containment shall not be repressurized beyond 50 percent of the containment design pressure.
When the Commission issued what is now paragraph c(3)(ii) of 10 CFR 50.44 in 1981, a safety related hydrogen recombiner system was installed. Paragraph c(3)(ii) requires:
By the end of the first scheduled outage beginning after July 5, 1982 and of sufficient duration to permit required modifications, each light-water nuclear power reactor that relies upon a purge/repressurization system as the primary means for controlling combustible gases following a LOCA shall be provided with either an internal recombiner or the capability to install an external recombiner following the start of an accident. The internal or external recombiners must meet the combustible gas control requirements in paragraph (d) of this section. [...]
As a result, the recombiner system became the primary method of combustible gas control while the PACV system became a backup method.
The purpose of this exemption request for 10 CFR 50.44(f) is to remove requirements for the PACV system from the IP3 licensing basis. The licensee is not requesting an exemption from GDC 41, Containment Atmosphere Cleanup, or 10 CFR 50.44(c). The licensee is requesting this exemption in accordance with 10 CFR 50.12. Pursuant to 10 CFR 50.12, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR Part 50 when (1) the exemptions are authorized by law, will not present an undue risk to public health or safety, and are consistent with the common defense and security; and (2) when special circumstances are present. These circumstances include the special circumstances stated in 10 CFR 50.12(a)(2)(ii), Application of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule. The PACV system also has a role in severe accident management. The Commission stated in Attachment 1 to SECY-02-0080, Proposed Rulemaking - Risk-Informed 10 CFR 50.44, Combustible Gas Control In Containment, their position concerning the ability to vent the containment as a severe accident strategy.
Specifically, Attachment 1 to SECY-02-0080 states:
The Commission continues to view severe accident management guidelines as an important part of the severe accident closure process. Severe accident management guidelines are part of a voluntary industry initiative to address accidents beyond the design basis and emergency operating instructions. In November 1994, the US nuclear industry committed to implement severe accident management at their plants by December 31, 1998, using the guidance contained in NEI 91-04, Revision 1, Severe Accident Issue Closure Guidelines. Generic severe accident management guidelines developed by each nuclear steam system supplier owners group includes either purging and venting or venting the containment to address combustible gas control. On the basis of the industry-wide commitment, the Commission is not proposing to require such capabilities, but continues to view purging and/or controlled venting of all containment types to be an important combustible gas control strategy that should be considered in a plants severe accident management guidelines.
3.0 DISCUSSION Pursuant to 10 CFR 50.12, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR Part 50
when (1) the exemptions are authorized by law, will not present an undue risk to public health or safety, and are consistent with the common defense and security; and (2) when special circumstances are present. These circumstances include the special circumstances that the PACV system is not needed to meet the underlying purpose of 10 CFR 50.44. As mentioned above, the underlying purpose of 10 CFR 50.44 is to show that following a LOCA, an uncontrolled hydrogen-oxygen recombination would not take place, or that the plant could withstand the consequences of uncontrolled hydrogen-oxygen recombination without loss of safety function.
The staff examined the licensees rationale to support the exemption request of eliminating the licensing basis requirements for the PACV system and concluded that retaining the licensing basis requirements for the PACV system is not necessary to achieve the underlying purpose of 10 CFR Part 50.44. As mentioned above, the PACV system is the backup combustible gas control system. The primary system is the electric hydrogen recombiner system which meets the requirements of 10 CFR 50.44 c(3)(ii). Each of the recombiner subsystems is capable of maintaining the hydrogen concentration below the required limit following a design-basis LOCA. The PACV system is not necessary to meet the intent of the rule.
In their January 16, 2003, letter, the licensee stated that even with the retirement of the PACV system, they will be able to meet all their severe accident management commitments.
Their current Severe Accident Management Guidelines (SAMGs) identify, in addition to the PACV system, three alternate methods of containment depressurization and combustible gas control. These methods are backflow to the steam ejector line, containment pressure relief line, and the containment purge system. The licensee stated that the decommissioning of the PACV system will include a revision to the SAMGs that will include the three alternative methods listed above. The staff concludes that the licensee continues to address the Commissions concerns
regarding the use of purging and/or controlled venting of containment as an important combustible gas control strategy that should be considered in the licensees severe accident management guidelines.
Based on the above, the staff determined that the requested exemption from the requirements of 10 CFR 50.44(f) meets the requirements of 10 CFR 50.12. The staff finds the requested exemption acceptable. Therefore, the staff concludes that pursuant to 10 CFR 50.12(a)(2) the licensees requested exemption from the requirements of 10 CFR 50.44(f) for IP3 as specified in a letter dated October 3, 2002, and as supplemented by letters dated January 16 and March 11, 2003, is acceptable.
4.0 CONCLUSION
Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12(a), the exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security. Also, special circumstances are present. Therefore, the Commission hereby grants ENO an exemption from the requirement to maintain a purge/repressurization system of 10 CFR 50.44(f) for IP3.
Pursuant to 10 CFR 51.32, the Commission has determined that the granting of this exemption will not have a significant effect on the quality of the human environment (68 FR 15487).
This exemption is effective upon issuance.
Dated at Rockville, Maryland, this 2nd day of April, 2003.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
John A. Zwolinski, Director Division of Licensing Project Management Office of Nuclear Reactor Regulation