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MONTHYEARML11154A0982011-05-25025 May 2011 License Amendment Request Pursuant to 10 CFR 50.90: Revision to License Condition 2.B.(2) to Delete Outdated Reference Project stage: Request ML1115905602011-06-0707 June 2011 E-mail from R.Guzman to J.Dosa Acceptance Review Determination for LAR to Revise License Condition 2.B.(2) to Delete Outdated Reference Project stage: Acceptance Review ML1218400802012-06-29029 June 2012 Revision to License Condition 2.B.(2) to Delete Outdated Reference - Response to NRC Request for Additional Information Project stage: Response to RAI ML1211601842012-07-30030 July 2012 Issuance of Amendment 213 Regarding Revision to License Condition 2.B.(2) to Delete Outdated Reference Project stage: Approval ML12219A2112012-08-0707 August 2012 Correction to Page 3 of the License - Nine Mile Point Nuclear Station, Unit No. 1 - Issuance of Amendment Regarding Revision to License Condition 2.B.(2) to Delete Outdated Reference Project stage: Approval 2012-06-29
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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023 Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12 NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station 2024-09-04
[Table view] Category:Report
MONTHYEARNMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . NMP1L3515, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-03-27027 March 2023 Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20190A1482020-07-0808 July 2020 FAQ 20-01 NMP Scram Final Approved ML20100F6822020-04-0909 April 2020 Submittal of Analytical Evaluation of Recirculation Discharge Nozzle-to-Safe End Weld Indication ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018 Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The. NMP1L3229, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ...2018-08-20020 August 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe ... ML18018B2922018-01-18018 January 2018 Appendix a, Justification for Continued Operation, Component Review Summary Sheet ML18018B2912018-01-18018 January 2018 Pipe Crack Task Force Report ML18018A9652018-01-18018 January 2018 Nine Mile Point, Unit 1 - Equipment Qualification Program and Tables I - Equipment Qualification Reports and Table Ii - TMI Action Plan ML18018B0122018-01-18018 January 2018 Semi-Annual Radioactive Effluent Release Report July-December 1999 ML17251A0452017-09-20020 September 2017 - Staff Assessment of Flooding Focused Evaluation (CACs No. MG0087 and MG0088) ML17109A3652017-04-13013 April 2017 Pressure and Temperature Limits Report ML17079A3842017-03-24024 March 2017 Summary of the U.S. Nuclear Regulatory Commission Staff'S Review of the Spring 2016 Steam Generator Tube Inservice Inspections ML17037A6862017-02-0606 February 2017 Table 7.2-1 ML17037A7032017-02-0606 February 2017 Table 7.2-1 (Cont'D) ML17027A0162017-01-27027 January 2017 10 CFR 50.46 Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors RS-16-178, High Frequency Supplement to Seismic Hazard Screening Report2016-11-0202 November 2016 High Frequency Supplement to Seismic Hazard Screening Report ML16231A4522016-08-30030 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events) ML16223A8532016-08-25025 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) RS-16-091, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2016-06-14014 June 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML16160A0942016-06-0808 June 2016 ASP ANALYSIS- REJECT- Nine Mile Point Unit 1 Automatic Reactor Scram Due to Main Steam Isolation Valve Closure (LER 220-2015-004) ML15153A6602015-06-16016 June 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Re ML15028A1492015-02-11011 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109, Severe Accident Capable Hardened Vents RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML15022A6612014-07-31031 July 2014 Stress Re-Evaluation of Nine Mile Point Unit 2 Steam Dryer at 115% CLTP, CDI Report No. 14-08NP, Revision 0, Non-proprietary Version ML14153A4102014-07-24024 July 2014 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14167A3492014-06-20020 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tac. MF0249 & MF0250) ML15022A6622014-05-31031 May 2014 Acoustic and Low Frequency Hydrodynamic Loads at 115% CLTP Target Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1R, C.D.I. Report No. 14-09NP, Revision 1, Non-proprietary Version ML15023A0312014-04-30030 April 2014 Computation of Cumulative Usage Factor for the 115% CLTP Power Level at Nine Mile Point Unit 2 with the Inboard RCIC Valve Closed, C.D.I. Technical Note No. 14-04NP, Revision 0, Non-proprietary Version ML14099A1962014-03-31031 March 2014 Constellation Energy Nuclear Group, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task. ML14064A3242014-02-28028 February 2014 000N2495-R1-NP, Rev. 0, Nine Mile Point Nuclear Station Unit 2 Comparison of Mellla+ Reference Design to Cycle 15 Design Characteristics. ML14071A4782014-02-21021 February 2014 Response to Nrc'S Request for Cashflow Statements Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments ML14351A4272014-01-31031 January 2014 000N2528-SRLR, Revision 1, Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988 Mwt) / MELLLA (99-105% Flow). ML14064A3222014-01-31031 January 2014 00N0123-SRLR, Rev. 2, Supplemental Reload Licensing Report for Nine Mile Point 2 (NMP2) Reload 14 Cycle 15 Extended Power Uprate (Epu)/Maximum Extended Load Line Limit Plus (Mellla+). ML14024A4422014-01-0707 January 2014 Submittal of Report in Accordance with 10 CFR 26.719(c)(1) Regarding Unsatisfactory Blind Performance Sample Testing ML14064A3232013-12-31031 December 2013 000N0123-FBIR-NP, Rev. 0, Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15. ML13225A5842013-12-19019 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13338A6632013-12-11011 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 1, TAC No.: MF1129 ML13338A6642013-12-11011 December 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Nine Mile Point, Unit 2, TAC No.: MF1130 ML13311A0542013-11-0404 November 2013 Pressure and Temperature Limits Report (PTLR) PTLR-2, Revision 0 (Draft B) ML13316B1102013-11-0101 November 2013 Attachment 9 - Global Nuclear Fuel Report GNF-0000-0156-7490-RO-NP, Gnf Additional Information Regarding the Requested Change to the Technical Specification SLMCPR, Dated August 26, 2013 (Non-proprietary) ML13311A0552013-09-30030 September 2013 Fluence Extrapolation in Support of NMP2 P-T Cure Update, MPM-913991, September 30, 2013, Attachment 3 ML13197A2222013-07-12012 July 2013 Supplemental Response to 10 CFR 50.54(f) Request for Information, Recommendation 2.3, Seismic 2024-07-24
[Table view] Category:Miscellaneous
MONTHYEARNMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3515, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-03-27027 March 2023 Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20190A1482020-07-0808 July 2020 FAQ 20-01 NMP Scram Final Approved ML18018B2922018-01-18018 January 2018 Appendix a, Justification for Continued Operation, Component Review Summary Sheet ML18018B2912018-01-18018 January 2018 Pipe Crack Task Force Report ML17251A0452017-09-20020 September 2017 - Staff Assessment of Flooding Focused Evaluation (CACs No. MG0087 and MG0088) ML17079A3842017-03-24024 March 2017 Summary of the U.S. Nuclear Regulatory Commission Staff'S Review of the Spring 2016 Steam Generator Tube Inservice Inspections ML17027A0162017-01-27027 January 2017 10 CFR 50.46 Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors RS-16-178, High Frequency Supplement to Seismic Hazard Screening Report2016-11-0202 November 2016 High Frequency Supplement to Seismic Hazard Screening Report ML16231A4522016-08-30030 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events) ML16223A8532016-08-25025 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) RS-16-091, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2016-06-14014 June 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML16160A0942016-06-0808 June 2016 ASP ANALYSIS- REJECT- Nine Mile Point Unit 1 Automatic Reactor Scram Due to Main Steam Isolation Valve Closure (LER 220-2015-004) ML15153A6602015-06-16016 June 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Re ML15028A1492015-02-11011 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109, Severe Accident Capable Hardened Vents ML14153A4102014-07-24024 July 2014 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML14167A3492014-06-20020 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tac. MF0249 & MF0250) ML14099A1962014-03-31031 March 2014 Constellation Energy Nuclear Group, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task. ML14024A4422014-01-0707 January 2014 Submittal of Report in Accordance with 10 CFR 26.719(c)(1) Regarding Unsatisfactory Blind Performance Sample Testing ML13066A1712013-02-28028 February 2013 R.E. Gina, Overall Integrated Plan for Mitigation Strategies for Beyond-Design-Basis External Events ML13037A0822013-01-31031 January 2013 Submittal of Supplemental Seismic Walkdown Report ML12312A0142012-09-17017 September 2012 Transmittal of Pressure and Temperature Limits Report Revision 02.00 ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML11154A0982011-05-25025 May 2011 License Amendment Request Pursuant to 10 CFR 50.90: Revision to License Condition 2.B.(2) to Delete Outdated Reference ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages ML1019504972010-07-0909 July 2010 Attachment 1, CDI Report No. 10-11NP, Stress Assessment of Nine Mile Point Unit 2 Steam Dryer Using the Acoustic Circuit Model Rev. 4.1, Rev. 0, Cover Through Chapter 5 ML1007000882010-03-0303 March 2010 Pressure and Temperature Limits Report Revision ML0911802792009-04-21021 April 2009 Core Operating Limits Report, COLR1-19, Revision 0 ML12220A1012008-11-24024 November 2008 Constellation Energy Group, Inc. Definitive Proxy Statement Schedule 14A ML0629702462006-10-16016 October 2006 Special Report: Channel #12 of the Containment Hydrogen Monitoring System Inoperable for Planned Preventive Maintenance ML0627700442006-09-29029 September 2006 State Pollutant Discharge Elimination System, Permit No. Ny 000 1015, Request for Information Re Environmental Benefit Permit Strategy ML0619503912006-07-0505 July 2006 Post Accident Monitoring Instrumentation Report: Division 2 of the Containment Monitoring System Inoperable ML0611804852006-04-28028 April 2006 NRC 2006 a, Gen&Sis - Census 2000 Low Income Ej Nine Mile Point License Renewal ML0610906202006-04-19019 April 2006 NYSDEC 2003k, Website Reference Used in Chapter 2 NMP FSEIS, Round Whitefish Fact Sheet. ML0608804422006-03-24024 March 2006 GE Evaluation of OPRM Performance During Instability Events at Nine Mile Point, Unit 2 and Perry Nuclear Power Plant ML0606703632006-02-27027 February 2006 Special Report: Channel #11 of the Containment Hydrogen Monitoring System Inoperable for Planned Preventive Maintenance ML0609404802005-06-15015 June 2005 Doe/Eia 2005, Website Reference Used in Chapter 8 NMP FSEIS ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement ML0430003332004-10-26026 October 2004 to Audit and Review Plan for Plant Aging Management Reviews and Programs for the Nine Mile Point Nuclear Station, Units 1 and 2. ML0609401922004-10-0505 October 2004 Ohio Department of Natural Resources, Website Reference Used in Chapter 2 NMP FSEIS ML0609401352004-08-24024 August 2004 NYSDEC 2003a, Website Reference Used in Chapter 2 NMP FSEIS ML0609400532004-07-28028 July 2004 Campus Program.Com 2004, Website Reference Used in Chapter 2 NMP FSEIS ML0421203072004-07-20020 July 2004 2004 Owner'S Activity Report for Inservice Examinations for Nine Mile Point Unit 2 ML0419501842004-07-0606 July 2004 Special Report, Channel #11 of the Containment Hydrogen Monitoring System Removed from Service for Planned Maintenance ML0330702722003-10-23023 October 2003 10CFR50.59 Evaluation Summary Report for 2003 ML0323304182003-08-13013 August 2003 Guarantee of Retrospective Premium ML0318909502003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-duty Enhancements for Nuclear Security Force Personnel for Calvert Cliffs, ML0619303922002-10-31031 October 2002 Identification of Changes, Reasons and Bases for Nine Mile Point Nuclear Station, L.L.C., Quality Assurance Program Topical Report, Nine Mile Point Nuclear Station - Unit 2 (USAR Appendix B) 2024-07-24
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Thomas A. Lynch P.O. Box 63 Plant General Manager Lycoming, New York 13093 315.349.5205 315.349.1321 Fax CENGS.
a joint venture of 0 Constellation ~ D NINE MILE POINT NUCLEAR STATION May 25, 2011 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
Nine Mile Point Nuclear Station Unit No. 1, Docket No. 50-220 License Amendment Request Pursuant to 10 CFR 50.90: Revision to License Condition 2.B.(2) to Delete Outdated Reference Pursuant to 10 CFR 50.90, Nine Mile Point Nuclear Station, LLC (NMPNS) hereby requests an amendment to Nine Mile Point Unit 1 (NMP1) Renewed Facility Operating License DPR-63. The proposed license amendment would delete reference to a specific date delineated in License Condition 2.B.(2).
License Condition 2.B.(2) reads as follows:
Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended as of February 4, 1976; Since February 4, 1976, several license amendment requests (LARs) to increase the NMPI spent fuel pool storage capacity have been submitted to and approved by the Commission. These LARs resulted in changes to Technical Specification (TS) Section 5.0, "Design Features," Subsection 5.5, "Storage of Unirradiated and Spent Fuel," and to the NMP1 Updated Final Analysis Report. However, License 0coo
Document Control Desk May 25, 2011 Page 2 Condition 2.B.(2) should also have been revised to reflect these changes. NMPNS proposes to delete the outdated reference to February 4, 1976, to address this omission.
The Enclosure to this letter provides a description and basis for the proposed change and a marked-up copy of the existing operating license page indicating the proposed change. NMPNS has concluded that the activities associated with the proposed amendment represent no significant hazards consideration under the standards set forth in 10 CFR 50.92. There are no regulatory commitments identified in this submittal.
NMPNS requests approval of the proposed license amendment by May 25, 2012, with implementation within 90 days of receipt of the approved amendment.
Pursuant to 10 CFR 50.91(b)(1), NMPNS has provided a copy of this license amendment request, with Enclosure, to the appropriate state representative.
Should you have any questions regarding the information in this submittal, please contact John J. Dosa, Director Licensing, at (315) 349-5219.
Very truly yours,
Document Control Desk May 25, 2011 Page 3 STATE OF NEW YORK TO WIT:
COUNTY OF OSWEGO I, Thomas A. Lynch, being duly sworn, state that I am the Nine Mile Point Plant General Manager, and I am duly authorized to execute and file this license amendment request on behalf of Nine Mile Point Nuclear Station, LLC. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other Nine Mile Point employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.
Subscribed and sworn befor me, a Notary Public in and for the State of New York and County of y ,this his f.J
&day of ,2011.
WITNESS my Hand and Notarial Seal: _____
- -7Notar-Pt/lic My Commission Expires:
TONYA LAI4f Date tOs~g Cqunty. Bog. No. 01 My Comriifiion Expires TAL/JMT
Enclosure:
Evaluation of the Proposed Change cc: NRC Regional Administrator, Region I NRC Resident Inspector NRC Project Manager A. L. Peterson, NYSERDA
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ENCLOSURE EVALUATION OF THE PROPOSED CHANGE TABLE OF CONTENTS 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION 2.1 Description of the Proposed Change 2.2 Background
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedent 4.3 Significant Hazards Consideration 4.4 Conclusions
5.0 ENVIRONMENTAL CONSIDERATION
6.0 REFERENCE ATTACHMENT
- 1. Proposed Operating License Change (Mark-up)
Nine Mile Point Nuclear Station, LLC May 25,2011
ENCLOSURE EVALUATION OF THE PROPOSED CHANGE 1.0
SUMMARY
DESCRIPTION This evaluation supports a request to amend Renewed Facility Operating License DPR-63 for Nine Mile Point Unit 1 (NMPI). The proposed license amendment would delete reference to a specific date delineated in License Condition 2.B.(2).
License Condition 2.B.(2) reads as follows:
Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended as of February 4, 1976; Since February 4, 1976, several license amendment requests (LARs) to increase the NMP1 spent fuel pool (SFP) storage capacity have been submitted to and approved by the Commission. These LARs resulted in changes to Technical Specification (TS) Section 5.0, "Design Features," Subsection 5.5, "Storage of Unirradiated and Spent Fuel," and to the NMP1 Updated Final Safety Analysis Report (UFSAR). However, License Condition 2.B.(2) should also have been revised to reflect these changes.
Nine Mile Point Nuclear Station, LLC (NMPNS) proposes to delete the outdated reference to February 4, 1976, to address this omission.
2.0 DETAILED DESCRIPTION 2.1 Description of the Proposed Change License Condition 2.B.(2) authorizes NMPNS to "... receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report as supplemented and amended as of February 4, 1976." The proposed change will remove the words "as of February 4, 1976," as shown in Attachment 1.
2.2 Background The current wording in License Condition 2.B.(2) was incorporated by License Amendment No. 11 issued on July 7, 1976 (Reference 1). Amendment No. 11 was based on a NMP1 amendment application dated February 4, 1976. The February 4, 1976, date was incorporated into License Condition 2.B.(2).
Since February 4, 1976, several LARs to increase the NMP 1 SFP storage capacity have been submitted to and approved by the Commission. These LARs resulted in changes to TS Section 5.0, "Design Features,"
Subsection 5.5, "Storage of Unirradiated and Spent Fuel," and to the NMPI UFSAR. Specific amendments include: (1) License Amendment No. 21, issued January 27, 1978, which increased the SFP capacity from 1140 to 1984 fuel assemblies; (2) License Amendment No. 54, issued February 1, 1984, which increased the SFP capacity from 1984 to 2776 fuel assemblies; and (3) License Amendment No.
167, issued June 17, 1999, which increased the SFP capacity from 2776 to 4086 fuel assemblies. In each instance, the reference to February 4, 1976, should have been updated (or deleted) as the increases in the allowed spent fuel storage capacity were greater than the limitations described in the UFSAR as of February 4, 1976.
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ENCLOSURE EVALUATION OF THE PROPOSED CHANGE
3.0 TECHNICAL EVALUATION
TS Section 5.5, "Storage of Unirradiated and Spent Fuel," and UFSAR Section X, "Reactor Auxiliary and Emergency Systems," Part J, "Fuel and Reactor Components Handling System," provide the specific limitations on the storage of fuel assemblies in the NMPI SFP as well as assemblies in the fresh fuel storage vault. Changes to the SFP storage capacity, as provided in TS Section 5.5, have been evaluated and approved by the NRC through the LAR process and then captured in the UFSAR. The current fuel pool storage capacity stated in the UFSAR is consistent with TS Section 5.5 and is based on Amendment No. 167 issued June 17, 1999, which increased the pool capacity from 2776 to 4086 fuel assemblies. The number of assemblies allowed in the fresh fuel storage vault as stated in the UFSAR is also consistent with TS Section 5.5. Removing the outdated reference to February 4, 1976, from License Condition 2.B.(2) has no effect on these limitations or on the supporting evaluations.
In addition to storage, License Condition 2.B.(2) also discusses the limitations of special nuclear material required for reactor operation. The number of fuel assemblies allowed in the reactor core is specified in TS Section 5.2, "Reactor," and is consistent with the current NMP1 UFSAR description. Removing the outdated reference to February 4, 1976, from License Condition 2.B.(2) has no effect on these limitations.
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria License Condition 2.B.(2) authorizes NMPNS, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended (as of February 4, 1976). The stipulated conditions and requirements of License Condition 2.B.(2) are not affected by the proposed change to remove the outdated reference. In addition, the limitations delineated in TS Section 5.0 and the UFSAR regarding SFP storage capacity, new fuel storage, and fuel assemblies in the reactor core will be maintained.
4.2 Precedent The proposed wording for NMP1 License Condition 2.B.(2) is consistent with the wording found in the corresponding license condition at multiple stations including Calvert Cliffs Units I and 2 and Nine Mile Point Unit 2.
4.3 Significant Hazards Consideration Nine Mile Point Nuclear Station, LLC (NMPNS) is requesting an amendment to Renewed Facility Operating License DPR-63 for Nine Mile Point Unit 1 (NMP1). License Condition 2.B.(2) authorizes NMPNS to "... receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended as of February 4, 1976." The proposed change would remove the outdated reference to February 4, 1976.
NMPNS has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
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ENCLOSURE EVALUATION OF THE PROPOSED CHANGE I. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The NMP1 Technical Specifications (TS) and Updated Final Safety Analysis Report (UFSAR) provide the specific limitations on the number of fuel assemblies in the NMP1 spent fuel pool, fresh fuel storage vault, and the reactor core. Removing the outdated reference to the February 4, 1976 UFSAR from License Condition 2.B.(2) has no effect on these limitations or on the supporting evaluations. The proposed change does not affect a precursor to any accident previously evaluated nor does it affect the ability of any system to mitigate the consequences of any accident previously evaluated.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The NMP1 TS and UFSAR provide the specific limitations on the number of fuel assemblies in the NMP I spent fuel pool, fresh fuel storage vault, and the reactor core. Removing the outdated reference to the February 4, 1976 UFSAR from License Condition 2.B.(2) has no effect on these limitations or on the supporting evaluations. The proposed change does not introduce a new mode of plant operation and does not involve a physical modification to the plant. The change will not introduce new accident initiators or impact the assumptions made in a safety analysis.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No.
Margin of safety is related to confidence in the ability of the fission product barriers to perform their design functions during and following postulated accidents. The NMP1 TS and UFSAR provide the specific limitations on the number of fuel assemblies in the NMP1 spent fuel pool, fresh fuel storage vault, and the reactor core. Removing the outdated reference to the February 4, 1976, UFSAR from License Condition 2.B.(2) has no effect on these limitations or on the supporting evaluations.
Accordingly, no margin of safety is affected.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, NMPNS concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
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ENCLOSURE EVALUATION OF THE PROPOSED CHANGE 4.4 Conclusions In conclusion, based on the considerations discussed above, (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 Commission's 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.
5.0 ENVIRONMENTAL CONSIDERATION
A review has determined that the proposed amendment would not change any requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, nor would it change an inspection or surveillance requirement. The proposed amendment does not involve:
(i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 REFERENCE
- 1. Letter dated July 7, 1976, Amendment No. 11 to the Nine Mile Point Unit 1 Facility Operating License, G. Lear (NRC) to G. Rhode (Niagara Mohawk Power Corporation) 4 of 4
ATTACHMENT 1 PROPOSED OPERATING LICENSE CHANGE (MARK-UP)
The current version of NMP1 Operating License (OL) Page 2 has been marked-up by hand to reflect the proposed change.
Nine Mile Point Nuclear Station, LLC May 25,2011
G. The licensee has satisfied the applicable provisions of 10 CFR Part 140 "Financial Protection Requirements and Indemnity Agreements" of the Commission's regulations; H. The issuance of this full-term renewed operating license will not be inimical to the common defense and security or to the health and safety of the public; After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the adverse environmental impacts of license renewal are not so great that preserving the option of license renewal would be unreasonable and the issuance of the full-term Renewed Facility Operating License No. DPR-63 (subject to the conditions for protection of the environment set forth herein) is in accordance with Appendix D, 10 CFR Part 50 of the Commission's regulations and all applicable requirements have been satisfied; and J. The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40 and 70 including Section 30.33, 40.32, 70.23 and 70.31. -
- 2. Renewed Facility Operating License No. DPR-63 is hereby issued to Nine Mile Point Nuclear Station, LLC to read as follows:
A. This license applies to the Nine Mile Point Nuclear Station Unit No. 1, a single cycle, force circulation, boiling light water reactor, and associated equipment (the facility), owned by Nine Mile Point Nuclear Station, LLC. The facility is located on the Nine Mile Point site on the southeast shore of Lake Ontario in Oswego County, New York and is described in the "Final Safety Analysis Report" (with its Amendments Nos. 3 through 13 and its Supplements Nos. 1 through 10) and the "Environmental Report" (with its Supplements Nos. 1through 3).
B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Nine Mile Point Nuclear Station, LLC:
(1) Pursuant to Section 104b of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," to possess, use, and operate the facility at the designated location in Oswego County, New York, in accordance with the procedures and limitations set forth in this amended license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described Safe nalysis Report, as supplemented and 4
amendedas of, ruaryj 9,6 Renewed Lziers~e No. BPR--63 Nv %'A '\ )JO,