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Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 05000003/20240022024-08-0606 August 2024 NRC Inspection Report 05000003/2024002, 05000247/2024002, 05000286/2024002 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 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) ML24080A1722024-03-20020 March 2024 Reply to a Notice of Violation EA-2024-010 IR 05000003/20240012024-03-20020 March 2024 NRC Inspection Report Nos. 05000003/2024001, 05000247/2024001, and 05000286/2024001 (Cover Letter Only) 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 IR 05000003/20230042024-02-22022 February 2024 NRC Inspection Report Nos. 05000003/2023004, 05000247/2023004, 05000286/2023004, and 07200051/2023004 and Notice of Violation 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 ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan 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 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 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 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 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 2024-09-18
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan 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 ML23243A9352023-11-30030 November 2023 Enclosure 1: Issuance IP LAR for Unit 2s Renewed Facility Licenses and PDTSs to Reflect Permanent Removal of Spent Fuel from SFPs ML23242A2742023-11-30030 November 2023 Enclosure 2: Issuance - IP Lar for Units 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs 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 ML22307A0452023-11-17017 November 2023 Enclosure 1 - Amendment No. 297 to Rfl No. DPR-26 for Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements with Spent Fuel Transfer to Dry Storage 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 ML21091A3052022-02-28028 February 2022 Issuance of Amendment No. 272 Revision to Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device (EPID L-2020-LLA-0051) (Non-Proprietary) ML21126A0082021-05-28028 May 2021 Enclosures 1-3, Conforming Amendment Nos. 64, 295, and 271, Transfer of Facility Licenses to Holtec International, Owner, and Holtec Decommissioning International, LLC, Operator ML21126A0052021-05-28028 May 2021 Letter, Issuance of Amendment Nos. 64, 295, and 271 Order Approving Transfer of Licenses and Conforming License Amendments ML21113A2002021-04-27027 April 2021 Correction to Amendment No. 294 Dated April 28, 2020, Permanently Defueled Technical Specifications ML21074A0002021-04-22022 April 2021 Issuance of Amendment No. 270 Permanently Defueled Technical Specifications ML21083A0002021-04-14014 April 2021 Issuance of Amendment No. 63 Permanently Defueled Technical Specifications ML20297A3262020-11-23023 November 2020 Enclosure 2, Draft Conforming Amendments for Transfer of Facility Operating Licenses to Holtec International, Owner, and Holtec Decommissioning International, LLC, Operator ML20100H9922020-06-0202 June 2020 Issuance of Amendment No. 269 Proposed Technical Specification Changes to City Water Surveillance Requirement and Condensate Storage Tank Required Action A.1 ML20122A2622020-05-0404 May 2020 Correction to Amendment No. 294 Dated April 28, 2020, Permanently Defueled Technical Specifications ML20081J4022020-04-28028 April 2020 Issuance of Amendment No. 294 Permanently Defueled Technical Specifications ML20071Q7172020-04-10010 April 2020 Issuance of Amendment Nos. 292 and No. 267 Changes to Technical Specification Sections 1.1, 4.0, and 5.0 for a Permanently Defueled Condition ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19209C9662019-09-0404 September 2019 Issuance of Amendment No. 290 Storage of Fresh and Spent Nuclear Fuel in the Spent Fuel Pool ML19065A1012019-03-21021 March 2019 Issuance of Amendment No. 61 and No. 289 Deletion of License Conditions Related to Decommissioning Trust Provision ML19072A1342019-03-15015 March 2019 Amended Provisional Operating License DPR-5, 3-22-2019 ML18337A4222018-12-20020 December 2018 Issuance of Amendment No. 265 One-Time Extension of 10 CFR Part 50, Appendix J, Type a, Integrated Leakage Rate Test Interval ML18212A1852018-09-17017 September 2018 Renewed Facility Operating License DPR-26, Technical Specifications, Appendix B ML18212A1882018-09-17017 September 2018 Renewed License Appendix C ML18212A1812018-09-17017 September 2018 Renewed Facility Operating License DPR-26, Technical Specifications, Appendix a ML18212A1902018-09-17017 September 2018 Renewed Facility Operating License DPR-64, Technical Specifications, Appendix a ML18212A1952018-09-17017 September 2018 Renewed Facility Operating License DPR-64, Technical Specifications, Appendix C ML18213A1142018-09-17017 September 2018 Renewed Facility Operating License ML17348A6952018-01-11011 January 2018 Issuance of Amendment Connection of Non-Seismic Boric Acid Recovery System to the Refueling Water Storage Tank (CAC No. MF9578; EPID L-2017-LLA-0202) ML17320A3542017-12-22022 December 2017 Issuance of Amendments Amendment of Inter-Unit Transfer of Spent Fuel (CAC Nos. MF8991 and MF8992; EPID L-2016-LLA-0039) NL-17-144, Proposed License Amendment Regarding Spent Fuel Storage2017-12-11011 December 2017 Proposed License Amendment Regarding Spent Fuel Storage NL-17-144, Indian Point Nuclear Generating Unit 2, Proposed License Amendment Regarding Spent Fuel Storage2017-12-11011 December 2017 Indian Point Nuclear Generating Unit 2, Proposed License Amendment Regarding Spent Fuel Storage ML17315A0002017-12-0808 December 2017 Issuance of Amendments Cyber Security Plan Implementation Schedule (CAC Nos. MF9656, MF9657, and MF9658; EPID: L-2017-LLA-0217) ML17025A2882017-01-30030 January 2017 Issuance of Amendments Application for Order to Transfer Master Decommissioning Trust from PASNY to Entergy ML16336A4922017-01-27027 January 2017 Transmittal Letter: Order Approving Transfer of Master Decommissioning Trust Funds for Indian Point, No. 3 & FitzPatrick Nuclear Plant from the Power Authority of the State of New York to Entergy Nuclear Operations, Inc. ML16215A2432016-11-15015 November 2016 Issuance of Amendment Nos. 285 and 261 Conditional Exemption from End-of-Life Moderator Temperature Coefficient ML16064A2152016-04-12012 April 2016 Issuance of Amendments Cyber Security Plan Implementation Schedule ML15349A7942016-02-23023 February 2016 Generation, Unit No. 2 - Issuance of Amendment Extension of the Containment Integrated Leak Rate Test to 15 Years ML14259A2182016-01-0505 January 2016 Issuance of Order and Conforming Amendments Concerning Stand Alone Weapons Preemption Authority ML15226A1592015-09-0303 September 2015 Issuance of Amendment Changes to Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection System Requirements ML15110A0092015-05-26026 May 2015 Issuance of Amendment Re Implementation of Technical Specification Task Force Traveler 510, Revision 2, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection(Tac Nos. MF3752 & MF3753) ML15083A4902015-04-0202 April 2015 Issuance of Amendment Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems ML15028A3082015-03-13013 March 2015 Issuance of Amendment Extension of the Type a Containment Integrated Leak Rate Test Frequency from 10 to 15 Years ML15050A1442015-03-0606 March 2015 Issuance of Amendments Proposed Change to Indian Point 3 Technical Specifications Regarding Reactor Vessel Pressure/Temperature Limit Curves (Tac No. MF3754) ML14316A5262014-12-11011 December 2014 Issuance of Amendments Cyber Security Plan Implementation Schedule (Tac Nos. MF3409 and MF3410) ML14265A3292014-09-24024 September 2014 Issuance of Amendment Temporary Change to Technical Specification 3.8.6 Battery 22 Surveillance Requirement (Exigent Circumstances) ML14198A1612014-09-0505 September 2014 Issuance of Amendment H* Alternate Repair Criteria for Steam Generator Tube Inspection and Repair (Tac No. MF3369) ML14169A5832014-07-17017 July 2014 Issuance of Amendment Revised Containment Integrity Analysis (Tac No. MF0591) ML14126A8092014-07-16016 July 2014 Issuance of Amendment Regarding Revisions to the Containment Analysis Licensing Basis 2023-12-05
[Table view] Category:Safety Evaluation
MONTHYEARML23339A0442023-12-0505 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 ML23243A8452023-11-30030 November 2023 Enclosure 3: Issuance - IP LAR for SE Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML23050A0022023-11-17017 November 2023 Enclosure 2 - Safety Evaluation for Indian Point Unit 2 License Amendment Request to Modify Technical Specifications for Staffing Requirements Following Spent Fuel Transfer to Dry Storage 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 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 ML23067A0822023-11-0101 November 2023 Enclosure 2 - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Safety Exemption Evaluation for Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML21091A3052022-02-28028 February 2022 Issuance of Amendment No. 272 Revision to Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device (EPID L-2020-LLA-0051) (Non-Proprietary) ML21074A0002021-04-22022 April 2021 Issuance of Amendment No. 270 Permanently Defueled Technical Specifications ML21083A0002021-04-14014 April 2021 Issuance of Amendment No. 63 Permanently Defueled Technical Specifications ML21054A3302021-02-24024 February 2021 Approval of Alternative IP3-ISI-RR-16 to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement ML20297A3332020-11-23023 November 2020 Enclosure 3, Safety Evaluation for Transfer of Renewed Facility Operating Licenses to Holtec International, Owner, and Holtec Decommissioning International, LLC, Operator ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI 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 ML20100H9922020-06-0202 June 2020 Issuance of Amendment No. 269 Proposed Technical Specification Changes to City Water Surveillance Requirement and Condensate Storage Tank Required Action A.1 ML20122A2622020-05-0404 May 2020 Correction to Amendment No. 294 Dated April 28, 2020, Permanently Defueled Technical Specifications ML20081J4022020-04-28028 April 2020 Issuance of Amendment No. 294 Permanently Defueled Technical Specifications ML20078L1402020-04-15015 April 2020 Issuance of Amendment Nos. 62, 293, and 268 Changes to Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML20099A1822020-04-13013 April 2020 Issuance of Relief Request IP3-IST-RR-001 - Alternative to Certain Requirements of the ASME Code for Extension of the Fourth 10-Year Inservice Test Interval ML20071Q7172020-04-10010 April 2020 Issuance of Amendment Nos. 292 and No. 267 Changes to Technical Specification Sections 1.1, 4.0, and 5.0 for a Permanently Defueled Condition ML19333B8682019-12-18018 December 2019 Approval of Certified Fuel Handler Training and Retraining Program ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19209C9662019-09-0404 September 2019 Issuance of Amendment No. 290 Storage of Fresh and Spent Nuclear Fuel in the Spent Fuel Pool ML19065A1012019-03-21021 March 2019 Issuance of Amendment No. 61 and No. 289 Deletion of License Conditions Related to Decommissioning Trust Provision ML19039A1492019-02-25025 February 2019 Issuance of Relief Request IP3-ISI-RR-14 Alternative Examination Required by ASME Code Case N-724-4 ML18337A4222018-12-20020 December 2018 Issuance of Amendment No. 265 One-Time Extension of 10 CFR Part 50, Appendix J, Type a, Integrated Leakage Rate Test Interval ML18251A0042018-09-18018 September 2018 Safety Evaluation for Relief Request IP3-ISI-RR-11, RR-12, RR-15 Approval of Alternative Associated with Extension of Fourth Interval Reactor Vessel and Piping Weld Inspections (EPID: L-2017-LLR-0124,0127) ML18193B0302018-07-18018 July 2018 Safety Evaluation for Relief Request IP3-ISI-RR-13 Fourth Ten-year Inservice Inspection Interval Extension ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 ML18142A4312018-05-31031 May 2018 Safety Evaluation for Relief Request IP2-ISI-RR-06 Approval of Alternative to Use Embedded Weld Repair ML18059A1562018-03-0606 March 2018 Safety Evaluation for Relief Request IP2-ISI-RR-05 Alternative Examination Volume Required by ASME Code Case N-729-4 ML18005A0662018-01-23023 January 2018 Safety Evaluation of Relief Requests ISI-RR-20, ISI-RR-21, and ISI-RR-22 Regarding the Fourth 10-Year Interval of the Inservice Inspection Program ML17348A6952018-01-11011 January 2018 Issuance of Amendment Connection of Non-Seismic Boric Acid Recovery System to the Refueling Water Storage Tank (CAC No. MF9578; EPID L-2017-LLA-0202) ML17320A3542017-12-22022 December 2017 Issuance of Amendments Amendment of Inter-Unit Transfer of Spent Fuel (CAC Nos. MF8991 and MF8992; EPID L-2016-LLA-0039) ML17315A0002017-12-0808 December 2017 Issuance of Amendments Cyber Security Plan Implementation Schedule (CAC Nos. MF9656, MF9657, and MF9658; EPID: L-2017-LLA-0217) ML17174B1442017-07-12012 July 2017 Relief Request for EN-ISI-16-1 Regarding Use of Later Edition and Addenda of the ASME Code ML17065A1712017-03-27027 March 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17069A2832017-03-16016 March 2017 Relief Request No. IP3-ISI-RR-09, for Alternative to the Depth Sizing Qualification Requirement ML16336A4922017-01-27027 January 2017 Transmittal Letter: Order Approving Transfer of Master Decommissioning Trust Funds for Indian Point, No. 3 & FitzPatrick Nuclear Plant from the Power Authority of the State of New York to Entergy Nuclear Operations, Inc. ML16358A4442017-01-11011 January 2017 Relief from the Requirements of the ASME Code Regarding Alternate IP3-RR-10 to the Full Circumferential Inspection Requirement of Code Case N-513-3 ML16215A2432016-11-15015 November 2016 Issuance of Amendment Nos. 285 and 261 Conditional Exemption from End-of-Life Moderator Temperature Coefficient ML16179A1782016-09-14014 September 2016 Safety Evaluation for Relief Request IP2-ISI-RR-01, Examination of Upper Pressurizer Welds ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16167A0812016-07-15015 July 2016 Request for Alternative IP2-ISI-RR-03 to Weld Reference System Examination Required by ASME Code Subarticle IWA-2600 ML16147A5192016-07-14014 July 2016 Safety Evaluation for Relief Request IP2-ISI-RR-02 Alternative Examination Volume Required by Code Case N-729-1 ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 ML16093A0282016-05-31031 May 2016 Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 ML16064A2152016-04-12012 April 2016 Issuance of Amendments Cyber Security Plan Implementation Schedule 2023-05-01
[Table view] |
Text
September 18, 2002 Mr. Michael R. 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. 2 - AMENDMENT RE:
GAS TURBINE GENERATOR FUEL OIL STORAGE (TAC NO. MB3919)
Dear Mr. Kansler:
The Commission has issued the enclosed Amendment No. 233 to Facility Operating License No. DPR-26 for the Indian Point Nuclear Generating Unit No. 2. The amendment consists of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated January 8, 2002, as supplemented on August 22, 2002.
The amendment revised TS Section 3.7.C, Gas Turbine Generators, and Section 4.6, Emergency Power System Periodic Tests, to change the minimum amount of fuel oil required to be stored from 54,200 gallons to 94,870 gallons. The proposed amendment also revised the minimum electrical output of the gas turbine generator that is required to be tested monthly to 2000 kW from the previous value of 750 kW.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely,
/RA/
Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-247
Enclosures:
- 1. Amendment No. 233 to DPR-26
- 2. Safety Evaluation cc w/encls: See next page
September 18, 2002 Mr. Michael R. 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. 2 - AMENDMENT RE:
GAS TURBINE GENERATOR FUEL OIL STORAGE (TAC NO. MB3919)
Dear Mr. Kansler:
The Commission has issued the enclosed Amendment No. 233 to Facility Operating License No. DPR-26 for the Indian Point Nuclear Generating Unit No. 2. The amendment consists of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated January 8, 2002, as supplemented on August 22, 2002.
The amendment revised TS Section 3.7.C, Gas Turbine Generators, and Section 4.6, Emergency Power System Periodic Tests, to change the minimum amount of fuel oil required to be stored from 54,200 gallons to 94,870 gallons. The proposed amendment also revised the minimum electrical output of the gas turbine generator that is required to be tested monthly to 2000 kW from the previous value of 750 kW.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely,
/RA/
Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-247
Enclosures:
- 1. Amendment No. 233 to DPR-26
- 2. Safety Evaluation cc w/encls: See next page Accession Number: ML022210010 *See previous concurrence OFFICE PDI-1\PM PDI-1\LA SPLB\SC* EEIB\SC* OGC* PDI-1\SC NAME PMilano SLittle EWeiss CHolden RWeisman RLaufer DATE 09/17/02 09/18/02 08/26/02 08/27/02 09/11/02 09/19/02 Official Record Copy
DATED: September 18, 2002 AMENDMENT NO. 233 TO FACILITY OPERATING LICENSE NO. DPR-26 INDIAN POINT UNIT 2 PUBLIC PDI-1 R/F OGC R. Laufer G. Hill (2)
W. Beckner ACRS B. Platchek, RI S. Little P. Milano E. Weiss D. Frumkin C. Holden J. Knox cc: Plant Service list
Indian Point Nuclear Generating Station Unit 2 Mr. Jerry Yelverton Ms. Charlene Fiason Chief Executive Officer Manager, Licensing Entergy Operations Entergy Nuclear Operations, Inc.
1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. Fred Dacimo Mr. John McCann Vice President - Operations Manager, Nuclear Safety and Licensing Entergy Nuclear Operations, Inc. Indian Point Nuclear Generating Unit 2 Indian Point Nuclear Generating Units 1 & 2 295 Broadway, Suite 1 295 Broadway, Suite 1 P. O. Box 249 P.O. Box 249 Buchanan, NY 10511-0249 Buchanan, NY 10511-0249 Mr. Harry P. Salmon, Jr.
Mr. Robert J. Barrett Director of Oversight Vice President - Operations Entergy Nuclear Operations, Inc.
Entergy Nuclear Operations, Inc. 440 Hamilton Avenue Indian Point Nuclear Generating Units 3 White Plains, NY 10601 295 Broadway, Suite 3 P.O. Box 308 Mr. John M. Fulton Buchanan, NY 10511-0308 Assistant General Counsel Entergy Nuclear Operations, Inc.
Mr. Dan Pace 440 Hamilton Avenue Vice President Engineering White Plains, NY 10601 Entergy Nuclear Operations, Inc.
440 Hamilton Avenue Mr. Thomas Walsh White Plains, NY 10601 Secretary - NFSC Entergy Nuclear Operations, Inc.
Mr. James Knubel Indian Point Nuclear Generating Unit 2 Vice President Operations Support 295 Broadway, Suite 1 Entergy Nuclear Operations, Inc. P. O. Box 249 440 Hamilton Avenue Buchanan, NY 10511-0249 White Plains, NY 10601 Regional Administrator, Region I Mr. Lawrence G. Temple U.S. Nuclear Regulatory Commission General Manager Operations 475 Allendale Road Entergy Nuclear Operations, Inc. King of Prussia, PA 19406 Indian Point Nuclear Generating Unit 2 295 Broadway, Suite 1 Senior Resident Inspector, Indian Point 2 P.O. Box 249 U. S. Nuclear Regulatory Commission Buchanan, NY 10511-0249 295 Broadway, Suite 1 P.O. Box 38 Mr. John Kelly Buchanan, NY 10511-0038 Director of Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
Indian Point Nuclear Generating Station Unit 2 Mr. William M. Flynn, President Alex Matthiessen New York State Energy, Research, and Executive Director Development Authority Riverkeeper, Inc.
17 Columbia Circle 25 Wing & Wing Albany, NY 12203-6399 Garrison, NY 10524 Mr. J. Spath, Program Director Paul Leventhal New York State Energy, Research, and The Nuclear Control Institute Development Authority 1000 Connecticut Avenue NW 17 Columbia Circle Suite 410 Albany, NY 12203-6399 Washington, DC, 20036 Mr. Paul Eddy Karl Copeland Electric Division Pace Environmental Litigation Clinic New York State Department 78 No. Broadway of Public Service White Plains, NY 10603 3 Empire State Plaza, 10th Floor Albany, NY 12223 Jim Riccio Greenpeace Mr. Charles Donaldson, Esquire 702 H Street, NW Assistant Attorney General Suite 300 New York Department of Law Washington, DC 20001 120 Broadway New York, NY 10271 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 Mr. Ray Albanese Executive Chair Four County Nuclear Safety Committee Westchester County Fire Training Center 4 Dana Road Valhalla, NY 10592 Ms. Stacey Lousteau Treasury Department Entergy Services, Inc.
639 Loyola Avenue Mail Stop: L-ENT-15E New Orleans, LA 70113
ENTERGY NUCLEAR INDIAN POINT 2, LLC ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-247 INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 233 License No. DPR-26
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Entergy Nuclear Operations, Inc. (the licensee) dated January 8, 2002, as supplemented on August 22, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-26 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 233, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 18, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 233 FACILITY OPERATING LICENSE NO. DPR-26 DOCKET NO. 50-247 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages 3.7-3 3.7-3 3.7-8 3.7-8 4.6-2 4.6-2 4.6-4 4.6-4
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 233 TO FACILITY OPERATING LICENSE NO. DPR-26 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247
1.0 INTRODUCTION
By letter dated January 8, 2002, as supplemented on August 22, 2002, Entergy Nuclear Operations, Inc. (ENO or the licensee) submitted a request for changes to the Indian Point Nuclear Generating Unit No. 2 (IP2) Technical Specifications (TSs). The requested changes would revise TS Section 3.7.C, Gas Turbine Generators, and Section 4.6, Emergency Power System Periodic Tests, to change the minimum amount of fuel oil required to be stored from 54,200 gallons to 94,870 gallons. The proposed change would also revise the minimum electrical output of the gas turbine (GT) generator that is required to be tested monthly to 2000 kilowatts (kW) from the previous value of 750 kW. The August 22, 2002, letter provided clarifying information that did not change the initial proposed no significant hazards consideration determination.
2.0 REGULATORY EVALUATION
The U.S. Nuclear Regulatory Commission (NRC) staff finds that ENO in its January 8, 2002, application identified the applicable regulatory requirements. The regulatory requirements which the staff considered in reviewing the proposed amendment are as follows:
- 1. Section III.G.3, Fire Protection of Safe Shutdown Capability, of Appendix R, Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979, to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50) requires fire protection features to be provided for structures, systems, and components important to safe shutdown.
- 2. Section III.L, Alternative and Dedicated Shutdown Capability, of Appendix R to 10 CFR Part 50 establishes the required capability of alternative and dedicated shutdown capability for a specific fire area.
- 3. 10 CFR 50.63, Loss of All Alternating Current [AC] Power, sets forth, in part, requirements for the capability of an alternate AC source power source to cope with station blackout (SBO).
- 4. Section 8.2.1, Network Interconnections, of the Updated Final Safety Analysis Report for IP2 states that the operability and surveillance requirements for the GTs ensure that the GTs can provide an alternate backup power source in case of loss of onsite emergency power and concurrent loss of offsite power as well as required auxiliary power for alternate safe shutdown systems equipment. In addition, it states that the minimum fuel inventory ensures that one GT will be capable of supplying the maximum electrical load for the alternate safe shutdown system for at least 3 days. Each GT generator is individually capable of supplying the required electrical load for alternate safe shutdown.
3.0 TECHNICAL EVALUATION
3.1 Background
Offsite power to IP2 is available from several sources consisting of two 138 kilovolt (kV) overhead supplies from the Buchanan 138 kV substation, three underground feeders from the 13.8 kV Buchanan substation, and three 13.8 kV combustion GTs. Each of the circuits is designed to be available in sufficient time following a loss of all onsite AC power supplies and other offsite electric power circuits to ensure that specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded. The independent alternate power systems are provided with adequate capacity and testability to supply the required engineered safety features and protection systems.
The normal source of auxiliary power for 6.9-kV buses 5 and 6 and standby power required during plant startup, shutdown, and after reactor trip is the station auxiliary transformer, which is supplied from the 138 kV system by either of two separate overhead lines from the Buchanan substation. Since the loss of this transformer would interrupt the 138 kV supply to the station, an alternate 13.8/6.9-kV supply is provided. Alternate feeds from the Buchanan 13.8 kV system are also available for immediate manual connection to the auxiliary buses. In addition, three GTs with blackstart (no auxiliary power) capability are available. The transfer from the normal to the reserve supply (or vice versa) must be accomplished manually. The three GTs may also serve to supply emergency shutdown power. The capacities of these GTs require that the station load be reduced to a minimum during startup.
Maximum flexibility of routing is provided by the inter-ties at the Buchanan substation (138 kV and 13.8 kV buses) and at the IP2 site (138 kV site switchyard and GT substation 6.9 kV bus tie). GT-1 is located adjacent to the IP Unit 1 turbine building. The position indication and controls for associated breakers are located on a panel in the Central Control Room. GT-2 and GT-3 are located at the Buchanan substation. Either of these GTs can supply power to the IP2 auxiliary electrical system through the Buchanan 13.8 kV distribution system connections or through the 138 kV tie lines.
The TSs regarding the operability and surveillance requirements for the GTs ensure that the GTs can provide an alternate backup power source in case of loss of onsite emergency power and concurrent loss of offsite power as well as required auxiliary power for alternate safe shutdown systems equipment. At least one GT is maintained operable at all times. This provides an additional contingency of backup electrical power for maintaining the plant in a safe shutdown condition.
The TS requirements also ensure that adequate onsite and offsite fuel inventories are maintained for both the diesel generators and the GT generators. The onsite fuel supply for GT-1 consists of two 30,000-gallon fuel oil tanks sufficient for operation at full load for 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> or at one-half load for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The fuel supply for GT-2 and GT-3 at Buchanan is supplied from a 200,000-gallon storage tank located at the Buchanan substation site. Currently, a minimum of 54,200 gallons of fuel is maintained available and dedicated for the required GT.
This minimum fuel inventory ensures that one GT will be capable of supplying the maximum electrical load for the IP2 alternate safe shutdown power supply system for at least 3 days.
Additional fuel oil suitable for the emergency diesel engines is stored on the site for GT-1 and at Buchanan for GT-2 and GT-3. A minimum additional storage of 29,000 gal is maintained in the storage tanks dedicated for diesel-generator use. This storage is sufficient for operation of two diesels for 112 hours0.0013 days <br />0.0311 hours <br />1.851852e-4 weeks <br />4.2616e-5 months <br /> at the minimum engineered safeguards load.
3.2 Station Blackout In response to the SBO Rule (10 CFR 50.63), the licensee credited the GT generators as an alternate ac (AAC) power source. As an AAC source, the GTs are available within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the onset of the SBO event and have sufficient capacity and capability to operate the systems necessary for coping with an SBO for a duration of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
3.3 Alternate Safe Shutdown The IP2 alternate safe shutdown system provides the necessary functions to maintain the plant in a safe shutdown condition following a fire that damages the capability to power and control essential equipment from normal and emergency IP2 sources. The alternate safe shutdown system including its functions, components, and operation is described in the "Indian Point Unit 2 Fire Protection Program Plan."
3.4 TS Changes for Fuel Oil Inventory In its January 8 application, the licensee stated that a revised calculation, that now indicates that the minimum level of fuel oil currently specified in the TS, does not ensure that there is sufficient GT generator fuel oil to power the auxiliary boiler feedwater (AFW) pump with the limiting combination of additional loads that may be required for post-fire safe shutdown for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The current TS Section 3.7.C, specifies that 54,200 gallons of fuel oil are required to assure that one GT generator will be capable of supplying the required electrical load for post-fire safe shutdown for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. A revised calculation was performed to include the loading for the motor-driven AFW pump and also includes more conservative assumptions. More conservative assumptions included assuming that the no-load fuel consumption is about 30% of the full load nominal consumption. The prior analysis had assumed no fuel oil was consumed at the no-load condition. Also, the revised calculation applies corrections to the nominal consumption curve to account for factors such as aging. Thus, the new minimum fuel oil inventory required was calculated to be 94,870 gallons.
3.5 Surveillance Requirement for Load Testing The tests specified in the TSs for the GTs are designed to assure that at least one GT will be available to provide power for operation of equipment, if required. The current IP2 alternate TS 4.6.D.1 assumed that the safe-shutdown power supply system demand would be for a maximum electrical load of approximately 750 kW. Thus, 750 kW was included as the required minimum test load in TS 4.6.D.1 to demonstrate adequate capability.
3.6 Staff Evaluation As set forth below, the specified test frequencies for the GTs and associated fuel supply will be adequate to identify and correct any mechanical or electrical deficiency before it can result in a component malfunction or failure. Based on the more conservative fuel oil consumption rates for the GTs, the licensee has increased the amount of fuel oil required in TS 3.7.C for the operable GT from 54,200 gallons to 94,870 gallons. The value was also revised in the associated basis. In increasing this value, the licensee will continue to meet the requirement that the GT will be capable of supplying more than the maximum electrical load for safe shutdown for 3 days (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />).
On the basis of the required loading and coping duration for an SBO event, the minimum fuel oil requirement of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for an SBO event is bounded by the 72-hour requirement for post-fire safe shutdown.
The licensee stated that the revised calculation also indicated that the electrical capacity required to be tested by TS is not sufficient to demonstrate capability to power post-fire safe shutdown loads. The current TS SR Section 4.6.D, Gas Turbine Generators, specifies that the GT generators shall be tested at a minimum load of 750 kW. For 10 CFR Part 50 Appendix R compliance, the licensee noted that the motor-driven AFW pump is available as a backup to the turbine-driven AFW pump. The previous minimum load rating considered only the minimum required loads and did not include the load from the motor-driven AFW pump.
The revised load rating of 1600 kW includes the motor-driven AFW pump in addition to the limiting combinations of additional loads that might be used for post-fire safe shutdown. The licensees proposal to add a 2000 kW test requirement to the TS is conservative, and confirms the ability of the GT generators to supply the loads needed to ensure post-fire safe shutdown.
3.7 Summary The proposed TS changes are based on a revised calculation that uses more conservative assumptions to determine the minimum inventory of fuel oil required and to determine the minimum load rating to be tested for the GTs. The proposed change increases the minimum GT fuel oil inventory and electrical output test loading in order to assure compliance with the SBO and alternate safe shutdown requirements of 10 CFR 50.62 and Appendix R to 10 CFR Part 50. These changes make the TSs consistent with the most current calculations regarding GT generator fuel oil supply and loading capability. Therefore, the staff finds the proposed TS changes acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (67 FR 10012). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: D. Frumkin J. Knox Date: September 18, 2002