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MONTHYEARML0601004672005-12-29029 December 2005 Application to Eliminate License Condition 2.F Requiring Reporting of Violations of Section 2.C of the Operating License Project stage: Request ML0618705072006-06-28028 June 2006 Technical Specifications Pages, Deletes the License Condition, Section 2.F, That Requires the Reporting of Violations in Section 2.C in the Operating License Project stage: Other ML0613000942006-06-28028 June 2006 Issuance of Amendment Eliminate License Condition 2.F Requiring Reporting of Violations of Section 2.C of the Operating License Project stage: Approval 2005-12-29
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Category:Letter
MONTHYEARNMP1L3570, 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 IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 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)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines 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 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) 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 . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - 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)2023-06-0909 June 2023 Day Commitment Response - 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) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NMP1L3484, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-15015 December 2022 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration NMP1L3477, License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise.2022-08-12012 August 2022 License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise. NMP1L3467, License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage2022-06-29029 June 2022 License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage NMP2L2799, License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators2022-05-24024 May 2022 License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-30030 September 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position NMP2L2762, License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2021-05-26026 May 2021 License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments NMP1L3369, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-12-18018 December 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process2020-04-30030 April 2020 License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process NMP2L2716, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-12-26026 December 2019 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors NMP2L2706, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.2019-10-31031 October 2019 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability NMP1L3278, License Amendment Request - Administrative Changes to the Technical Specifications2019-06-26026 June 2019 License Amendment Request - Administrative Changes to the Technical Specifications RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NMP2L2699, License Amendment Request to Revise Technical Specifications Main Steam Isolation Valve Leak Rate2019-05-31031 May 2019 License Amendment Request to Revise Technical Specifications Main Steam Isolation Valve Leak Rate RS-19-003, Application to Adopt TSTF-564, Safety Limit Mcpr.2019-02-0101 February 2019 Application to Adopt TSTF-564, Safety Limit Mcpr. NMP2L2694, Emergency License Amendment Request: One Time Extension to the High Pressure Core Spray Completion Time and Associated Surveillances2018-12-0606 December 2018 Emergency License Amendment Request: One Time Extension to the High Pressure Core Spray Completion Time and Associated Surveillances NMP1L3192, License Amendment Request - Revise Technical Specification 3.3.1 for Primary Containment Oxygen Concentration2018-06-26026 June 2018 License Amendment Request - Revise Technical Specification 3.3.1 for Primary Containment Oxygen Concentration RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) NMP1L3188, License Amendment Request - Proposed Change to Remove Boraflex Credit from Spent Fuel Racks2018-02-0909 February 2018 License Amendment Request - Proposed Change to Remove Boraflex Credit from Spent Fuel Racks NMP1L3142, License Amendment Request - Revise Technical Specifications to Apply TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-15015 December 2017 License Amendment Request - Revise Technical Specifications to Apply TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 RS-17-137, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-11-0808 November 2017 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NMP2L2660, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change2017-11-0303 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note2017-08-22022 August 2017 License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note NMP1L3158, Enclosure 4E - Procedure Matrix for Nine Mile Point Nuclear Station, Unit 12017-05-31031 May 2017 Enclosure 4E - Procedure Matrix for Nine Mile Point Nuclear Station, Unit 1 NMP2L2641, License Amendment Request - Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Revision 02017-05-31031 May 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Revision 0 ML17164A1532017-05-31031 May 2017 Enclosure 4B - EAL Red-Line Basis Document for Nine Mile Point Nuclear Station, Unit 1 ML17164A1552017-05-31031 May 2017 Enclosure 4D - EAL Front Matter for Nine Mile Point Nuclear Station, Unit 1 ML17164A1542017-05-31031 May 2017 Enclosure 4C - EAL Basis Document for Nine Mile Point Nuclear Station, Unit 1 JAFP-17-0050, Exigent License Amendment Request to Revise Emergency Action Level HU1.52017-05-19019 May 2017 Exigent License Amendment Request to Revise Emergency Action Level HU1.5 ML17037C4192017-05-11011 May 2017 Amendment to Operating License/Change to Appendix a of Technical Specification Concerning Certain Repairs at Facility and Concomitantly to Allow a Continuation of a Slightly Lower Water Level in the Reactor... NMP2L2643, License Amendment Request-Adoption of TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes2017-04-0505 April 2017 License Amendment Request-Adoption of TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP2L2639, Supplement to License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy- Nuclear 10 CFR Part 21 Safety Communication SC05-032017-02-17017 February 2017 Supplement to License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy- Nuclear 10 CFR Part 21 Safety Communication SC05-03 NMP1L3122, License Amendment Request - Proposed Changes Regarding Partial Length Fuel Rod (PLR) Burnup2017-01-0303 January 2017 License Amendment Request - Proposed Changes Regarding Partial Length Fuel Rod (PLR) Burnup NMP2L2584, License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy - Nuclear 1 O CFR Part 21 Safety Communication SC05-032016-12-13013 December 2016 License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy - Nuclear 1 O CFR Part 21 Safety Communication SC05-03 NMP2L2634, Emergency License Amendment Request - Proposed Changes to the High Pressure Core Spray System and Reactor Core Isolation Cooling System Actuation Instrumentation Technical Specifications2016-11-26026 November 2016 Emergency License Amendment Request - Proposed Changes to the High Pressure Core Spray System and Reactor Core Isolation Cooling System Actuation Instrumentation Technical Specifications 2023-08-21
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Constellation Energy P.O. Box 63 Lycoming, NY 13093 Nine Mile Point Nuclear Station December 29, 2005 NMP2L 2125 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001
SUBJECT:
Nine Mile Point Unit No. 2 Docket No. 50-4 10 Facility Operating License No. NPF-69 Application to Eliminate License Condition 2.F Requiring Reporting of Violations of Section 2.C of the Operating License Gentlemen:
In accordance with the provisions of Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), Nine Mile Point Nuclear Station, LLC (NMPNS) is submitting a request for an amendment to the operating license for Nine Mile Point Unit 2.
The proposed amendment would delete the license condition that requires reporting of violations of other requirements (i.e., conditions listed in Section 2.C) in the operating license. The change is consistent with the notice published in the FederalRegister on November 4, 2005, as part of the consolidated line item improvement process (CLIIP). provides a description of the proposed change and confirmation of applicability. provides the existing operating license page marked-up to show the proposed change.
NMPNS requests approval of the proposed license amendment by June 30, 2006, with the amendment being implemented within 60 days of the approval.
In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated New York State Official.
Page 2 NMP2L 2125 If you should have any questions regarding this submittal, please contact James Hutton, Director Licensing, at (315) 349-1041.
TJO/JJD/sac STATE OF NEW YORK :
- TO WIT:
COUNTY OF OSWEGO :
I, Timothy J. O'Connor, being duly sworn, state that I am the Plant General Manager, and that I am duly authorized to execute and file this 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 c mpany pract e and I believe it to be reliable.
Subscribed and swoZ1 efore me, a Notary Public in and for the of N ork and County of Oswego, this o/ day of0**ui~ *j 2005.
WITNESS my Hand and Notarial Seal: /j
- My Commission Expires:
/ - '"Date THEM=AL C!AL,..r lUSCoURr ta NO.IC 71 6 UTtOUiMEt A2+/-.
Page 3 NMP2L 2125 Attachments:
- 1. Description and Assessment
- 2. Proposed Nine Mile Point Unit 2 Operating License Changes (Mark-up) cc: Mr. S. J. Collins, NRC Regional Administrator, Region I Mr. L. M. Cline, NRC Senior Resident Inspector Mr. T. G. Colburn, Senior Project Manager, NRR (2 copies)
Mr. J. P. Spath, NYSERDA
ATTACHMENT I Description and Assessment
1.0 INTRODUCTION
The proposed amendment would delete Section 2.F of Facility Operating License No. NPF-69 for Nine Mile Point Unit 2 (NMP2), which requires reporting of violations of the requirements in Section 2.C of the facility operating license. The availability of this operating license improvement was announced in the FederalRegister on November 4, 2005, as part of the consolidated line item improvement process (CLIIP).
2.0 DESCRIPTION
OF PROPOSED AMENDMENT Consistent with the CLIIP Notice of Availability (70 FR 67202), the proposed amendment consists of deleting Section 2.F of Facility Operating License No. NPF-69. The current requirements of the license condition are as follows:
2.F Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, Nine Mile Point Nuclear Station, LLC shall report any violations of the requirements contained in Section 2.C of this license in the following manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System, with written followup within 30 days in accordance with the procedures described in 10 CFR 50.73(b),
(c), and (e).
The existing conditions in Section 2.C that are subject to the current reporting requirement consist of the following:
2.C(l) Maximum Power Level Nine Mile Point Nuclear Station, LLC is authorized to operate the facility at reactor core power levels not in excess of 3467 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
2.C(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 100 are hereby incorporated into this license.
Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
2.C(3) Fuel Storage and Handling (Section 9.1. SSER 4)
- a. Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.
Page 1 of 6
- b. When not in the reactor vessel, no more than three fuel assemblies shall be allowed outside of their shipping containers or storage racks in the New Fuel Vault or Spent Fuel Storage Facility.
- c. The above three fuel assemblies shall maintain a minimum edge-to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations.
- d. The New Fuel Storage Vault shall have no more than ten fresh fuel assemblies uncovered at any one time.
2.C(4) Turbine System Maintenance Program (Section 3.5.1.3.10. SER)
The operating licensee shall submit for NRC approval by October 31, 1989, a turbine system maintenance program based on the manufacturer's calculations of missile generation probabilities. (Submitted by NMPC letter dated October 30, 1989 from C.D. Terry and approved by NRC letter dated March 15, 1990 from Robert Martin to Mr. Lawrence Burkhardt, III).
2.C(5) Inservice Inspection (Sections 5.2.4.3 and 6.6.3. SSER 5)
The operating licensee shall submit an inservice inspection program in accordance with 10 CFR § 50.55a(g)(4) for staff review by July 31, 1987.
2.C(6) Initial Startup Test Program (Section 14. SER. SSERs 4 and 5)
Any changes to the Initial Test Program described in Section 14 of the Final Safety Analysis Report made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
2.C(7) Operation with Reduced Feedwater Temperature (Section 15.1, SSER 4)
Nine Mile Point Nuclear Station, LLC shall not operate the facility with reduced feedwater temperature for the purpose of extending the normal fuel cycle. The facility shall not be operated with a feedwater heating capacity less than that required to produce a feedwater temperature of 4050 F at rated steady-state conditions unless analyses supporting such operations are submitted by Nine Mile Point Nuclear Station, LLC and approved by the staff.
2.C(8) Safety Parameter Display System (SPDS) (Section 18.2, SSERs 3 and 5)
Prior to startup following the first refueling outage, the operating licensee shall have operational an SPDS that includes the revisions described in their letter of November 19, 1985. Before declaring the SPDS operational, the operating licensee shall complete testing adequate to ensure that no safety concerns exist regarding the operation of the Nine Mile Point Nuclear Station, Unit No. 2 SPDS.
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2.C(9) Detailed Control Room Design Review (Section 18.1. SSERs 5 and 6)
(a) Deleted per Amendment No. 24 (12-18-90)
(b) Prior to startup following the first refueling outage, the operating licensee shall provide the results of the reevaluation of normally lit and nuisance alarms for NRC review in accordance with its August 21, 1986 letter.
(c) Prior to startup following the first refueling outage, the operating licensee shall complete permanent zone banding of meters in accordance with its August 4, 1986 letter.
2.C(10) Additional Condition 1 The operating licensee is authorized by Amendment No. 91 to relocate certain Technical Specification requirements previously included in Appendix A to licensee-controlled documents, as described in Table R, Relocated Specifications and Removal of Details Matrix, attached to the NRC Staffs safety evaluation dated February 15, 2000, enclosed with the amendment.
Implementation of Amendment No. 91 shall include the relocation of these requirements to the appropriate documents, which shall be completed no later than December 31, 2000. The relocations to the Updated Safety Analysis Report shall be reflected in updates completed in accordance with 10 CFR 50.71(e).
2.C(l 1) Additional Condition 2 The schedule for performing Surveillance Requirements (SRs) that are new or revised in Amendment No. 91 shall be as follows:
For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval that begins on the date of implementation of this amendment.
For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.
For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.
For SRs that existed prior to this amendment whose intervals of performance are being extended, the first extended surveillance interval begins upon Page 3 of 6
completion of the last surveillance performed prior to the implementation of this amendment.
2.C(1 Ia) Additional Condition 3 The operating licensee shall be capable of establishing containment hydrogen monitoring within 90 minutes of initiating emergency core cooling (safety injection) following a loss of coolant accident.
2.C(12) On the closing date(s) of the transfer of the NMPC, RG&E, CHGEC, and NYSEG interests in NMP-2 to it, Nine Mile Point Nuclear Station, LLC shall:
(1) obtain from the transferors then transferring their interests all of their accumulated decommissioning trust funds for NMP-2, and (2) receive a parent company guarantee pursuant to 10 CFR 50.75(e)(1)(iii)(B) (to be updated annually) in a form acceptable to the NRC and in an amount which, when combined with the decommissioning trust funds for NMP-2 that have been transferred, equals or exceeds the total amounts for NMP LLC's then resulting total ownership share of NMP-2, respectively, pursuant to 10 CFR 50.75(b) and (c).
2.C(13) The decommissioning trust agreement for NMP-2, at the time any subject direct transfer is effected and thereafter, is subject to the following:
- a. The decommissioning trust agreement must be in a form acceptable to the NRC.
- b. With respect to the decommissioning trust funds, investments in the securities or other obligations of Constellation Energy Group, Inc., New Controlled, or their affiliates, successors, or assigns, are and shall be prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are and shall be prohibited.
- c. The decommissioning trust agreement must provide that no disbursements of payments from the trusts, other than for ordinary administrative expenses, shall be made by the trustee unless the trustee has given the NRC 30 days prior written notice of the payment. The decommissioning trust agreement shall fiurther contain a provision that no disbursements or payments from the trusts shall be made if the trustee receives prior written notice of objection from the Director of the Office of Nuclear Reactor Regulation.
- d. The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.
- e. The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the Page 4 of 6
investments made in the trusts shall adhere to a "prudent investor" standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commission's regulations.
2.C(14) NMP LLC shall take all necessary steps to ensure that the decommissioning trusts are maintained in accordance with the Application for approval of the transfer of the Unit 2 license to NMP LLC (Application), the requirements of the Order approving the transfer, and the related safety evaluation.
2.C(15) At the time any subject direct transfer is effected, NMP LLC shall enter or shall have entered into an intercompany credit agreement with Constellation Energy Group (CEG), Inc., or New Controlled, whichever entity is the ultimate parent of NMP LLC at that time, in the form and on the terms represented in the Application for license transfer. Should New Controlled become the ultimate parent of NMP LLC following the direct transfer of the license to NMP LLC, NMP LLC shall enter or shall have entered into a substantially identical intercompany credit agreement with New Controlled at the time New Controlled becomes the ultimate parent; in such case, any existing intercompany credit agreement with CEG, Inc. may be canceled once the intercompany credit agreement with New Controlled is established. Except as otherwise provided above, NMP LLC shall take no action to void, cancel, or modify any intercompany credit agreement referenced above, without the prior written consent of the Director of the Office of Nuclear Reactor Regulation.
2.C(16) Reactor Vessel Integrated Surveillance Program NMP LLC is authorized to revise the Updated Safety Analysis Report (USAR) to allow implementation of the Boiling Water Reactor Vessel and Internals Project reactor pressure vessel Integrated Surveillance Program as the basis for demonstrating compliance with the requirements of Appendix H to Title 10 of the Code of FederalRegulations, Part 50, "Reactor Vessel Material Surveillance Program Requirements," as set forth in the licensee's application dated January 9, 2004, and as supplemented on June 17, 2004.
3.0 BACKGROUND
The background for this application is adequately addressed by the NRC Notice of Availability published on November 4, 2005 (70 FR 67202) and the Notice of Opportunity to Comment published on August 29, 2005 (70 FR 51098).
4.0 REGULATORY REQUIREMENTS AND GUIDANCE The applicable regulatory requirements and guidance associated with this application are adequately addressed by the NRC Notice of Availability published on November 4, 2005 (70 FR 67202) and the Notice of Opportunity to Comment published on August 29, 2005 (70 FR 51098).
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5.0 TECHNICAL ANALYSIS
Nine Mile Point Nuclear Station, LLC (NMPNS) has reviewed the safety evaluation (SE) published on August 29, 2005, as part of the CLIIP Notice of Opportunity to Comment.
NMPNS has concluded that the justifications presented in the SE prepared by the NRC staff are applicable to NMP2 and justify this amendment of the facility operating license for NMP2.
6.0 REGULATORY ANALYSIS
A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC Notice of Opportunity to Comment published on August 29, 2005 (70 FR 51098).
7.0 NO SIGNIFICANT HAZARDS CONSIDERATION NMPNS has reviewed the proposed no significant hazards consideration determination published on August 29, 2005 (70 FR 51098), as part of the CLIIP Notice of Opportunity to Comment.
NMPNS has concluded that the proposed determination presented in the notice is applicable to NMP2 and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).
8.0 ENVIRONMENTAL EVALUATION NMPNS has reviewed the environmental evaluation included in the model SE published on August 29, 2005 (70 FR 51098), as part of the CLIIP Notice of Opportunity to Comment.
NMPNS has concluded that the staff's findings presented in that evaluation are applicable to NMP2 and the evaluation is hereby incorporated by reference for this application.
9.0 PRECEDENT This application is being made in accordance with the CLIIP. NMPNS is not proposing variations or deviations from the changes described in the NRC staffs model SE published on August 29, 2005 (70 FR 51098).
10.0 REFERENCES
- 1. FederalRegister Notice of Opportunity to Comment on Model Safety Evaluation on Elimination of Typical License Condition Requiring Reporting of Violations of Section 2.C of Operating License Using the Consolidated Line Item Improvement Process, August 29, 2005 (70 FR 51098).
- 2. FederalRegisterNotice of Availability of Model Application Concerning Elimination of Typical License Condition Requiring Reporting of Violations of Section 2.C of Operating License Using the Consolidated Line Item Improvement Process, November 4, 2005 (70 FR 67202).
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ATTACHMENT 2 PROPOSED NINE MILE POINT UNIT 2 OPERATING LICENSE CHANGES (MARK-UP)
v) A schedular exemption to GDC 50, Appendix Ato 10 CFR Part 50 to allow the operating licensee until start-up following the 'mini-outage,3 which is to occur within 12 months of commencing power operation (entering Operational Condition 1), to Install redundant fuses incircuits that use transfommers for redundant penetration protection in accordance with their letter of August 29, 1986 (NMP2L 0860). (Section 8.4.2, SSER 5) vi) A schedular exemption to 10 CFR 50.55a(h) for the Neutron Monitoring System until completion of the first refueling outage to allow the operating licensee to provide qualified Isolation devices for Class 1Elnon-1E interfaces described in their letters of June 23, 1987 (NMP2L 1057) and June 25, 1987 (NMP2L 1058).
(Section 7.2.2.10, SSER 6).
For the schedular exemptions in iv), v), and vi), above, the operating licensee, in accordance with Its letter of October 31, 1986, shall certify that all systems, components, and modifications have been completed to meet the requirements of the regulations for which the exemptions have been granted and shall provide a summary description of actions taken to ensure that the regulations have been met. This certification and summary shall be provided 10 days prior to the expiration of each exemption period as described above.
The exemptions set forth Inthis Section 2.D are authorized by law, will not present an undue risk to public health and safety, and are consistent with the common defense and security. These exemptions are hereby granted. The special circumstances regarding each exemption are identified in the referenced section of the Safety Evaluation Report and the supplements thereto. The exemptions inii) through vi) are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate to the extent authorized herein, Inconformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
E. Nine Mile Point Nudear Station, LLC shall fully implement and maintain in effect all safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21 Isentitied 'Nine Mile Point Nuclear Station, LLC Physical Security, Safeguards Contingency, and Security Training and Qualification Plan, Revision 0, and was submitted by letter dated October 15, 2004, as supplemented by letter dated October 25, 2004. Changes made in accordance with 10 CFR 73.55 shall be im lemented In rdance with the schedule set forth therein.
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Amendment No. ER 100 -144 Revised by lettor dated Octobor 28, 2004