Category:Letter type:NMP
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Pages in category "Letter type:NMP"
The following 195 pages are in this category, out of 195 total.
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- NMP1L2956, License Amendment Request Pursuant to 10 CFR 50.90: Change to Technical Specification Requirement Regarding Education and Experience Eligibility Requirements for Licensed Operators
- NMP1L2980, 10 CFR 50.46 30-Day Report
- NMP1L2994, 10 CFR 50.46 Annual Report
- NMP1L3001, Response to Apparent Violations in Inspection Report No. 05000220 & 05000410/2014005; EA-14-192
- NMP1L3023, Reactor Vessel Surveillance Capsule
- NMP1L3026, License Amendment Request- Proposed Changes to the Technical Specifications to Address Secondary Containment Personnel Access Door Openings
- NMP1L3027, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)
- NMP1L3051, Submittal of Relief Requests I3R-10, 1ISI-004, and 2ISI-013 Concerning Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements
- NMP1L3054, Response to Request for Additional Information No. 1 - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee....
- NMP1L3055, Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee....
- NMP1L3056, Proposed Alternative to Utilize Code Case N-789, Alternative Requirements Forvpad Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping for Raw Water Service
- NMP1L3058, Supplemental Response to Request for Additional Information 1 - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements...
- NMP1L3064, Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements....
- NMP1L3068, Supplemental Information to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to A....
- NMP1L3070, License Amendment Request - Reactivity Anomalies Surveillance
- NMP1L3082, Radioactive Effluent Release Report for 2015
- NMP1L3095, License Amendment Request - Proposed Revision to Technical Specifications in Response to GE Energy - Nuclear 10 CFR Part 21 Safety Communication SC05-03
- NMP1L3101, Reactor Vessel Surveillance Capsule to Remain in Spent Fuel Pool
- NMP1L3122, License Amendment Request - Proposed Changes Regarding Partial Length Fuel Rod (PLR) Burnup
- NMP1L3123, Request for Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J
- NMP1L3129, LER 17-01-00 for Nine Mile Point Unit 1 Manual Reactor Scram Due to High Turbine Vibration
- NMP1L3134, Core Operating Limits Report
- NMP1L3137, Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)
- NMP1L3142, License Amendment Request - Revise Technical Specifications to Apply TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
- NMP1L3143, Submittal of Core Operating Limits Report Cycle 23, Revision 3
- NMP1L3146, Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J
- NMP1L3150, Independent Spent Fuel Storage Installation, Submittal of 2016 Radioactive Effluent Release Report
- NMP1L3151, Submittal of 2016 Annual Radiological Environmental Operating Report
- NMP1L3161, Submittal of Radiological Emergency Plan Addendum and Implementing Procedure Revisions
- NMP1L3167, General License 30-Day Cask Registration Notification and Thermal Performance Assessment
- NMP1L3174, Transmittal of Radiological Emergency Plan Addendum Revision
- NMP1L3180, Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)
- NMP1L3186, Nine Mile Point Nuclear Station, Units 1 and 2 - Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents
- NMP1L3186, Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable ...
- NMP1L3188, License Amendment Request - Proposed Change to Remove Boraflex Credit from Spent Fuel Racks
- NMP1L3192, License Amendment Request - Revise Technical Specification 3.3.1 for Primary Containment Oxygen Concentration
- NMP1L3197, Submittal of 1O CFR 50.46 Annual Reporting Information
- NMP1L3201, Submittal of Radiological Emergency Plan Annex and Addendum Revisions
- NMP1L3206, Co., Submittal of Emergency Plan Revision
- NMP1L3206, Exelon Generation Co., Submittal of Emergency Plan Revision
- NMP1L3211, Independent Spent Fuel Storage Installation - 2017 Radioactive Effluent Release Report
- NMP1L3212, Submittal of 2017 Annual Radiological Environmental Operating Report
- NMP1L3215, Relief Requests Associated with Fifth and Fourth Ten-Year Lnservice Testing Intervals - Supplement 1
- NMP1L3221, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes.
- NMP1L3226, Submittal of Relief Requests Associated with the Fifth and Fourth Lnservice Inspection Intervals
- 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 ...
- NMP1L3233, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039)
- NMP1L3238, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, ...
- NMP1L3248, Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pre
- NMP1L3254, Submittal of Radiological Emergency Plan Addendum Revisions
- NMP1L3259, 10 CFR 50.46 Annual Report
- NMP1L3264, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Contain
- NMP1L3273, 2018 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2
- NMP1L3278, License Amendment Request - Administrative Changes to the Technical Specifications
- NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants
- NMP1L3281, Supplemental Information to Support Review of License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Containment Oxygen Concentration
- NMP1L3288, Fitness-for-Duty Response to Request for Information
- NMP1L3303, General License 30-day Cask Registration Notification and Thermal Performance Assessment
- NMP1L3304, Supplemental Information No. 2 to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Containment Oxygen Concentration
- NMP1L3309, Submittal of the Snubber IST Program Plan for the Unit 1 Fifth 10-Year Interval and the Unit 2 Fourth 10-Year Interval
- NMP1L3325, 10 CFR 50.46 Annual Report
- NMP1L3336, Independent Spent Fuel Storage Installation (ISFSI) - Submittal of 2019 Radioactive Effluent Release Report
- NMP1L3339, R. E. Ginna Station - Constellation Energy Group, LLC: Notification of Change in Indirect Ownership
- NMP1L3340, Annual Radiological Environmental Operating Report
- NMP1L3351, and Nine Mile Point Nuclear Station, Unit 1 - Request for Exemptions from 10 CFR 2.109(b)
- NMP1L3355, Letters to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
- NMP1L3356, Relief Requests Associated with Pump Periodic Verification Tests for the Fifth Ten-Year Inservice Test Interval
- NMP1L3361, Summary of Regulatory Commitment Changes
- NMP1L3362, Request for an Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding 2020 Annual Force-on-Force (FOF) Exercises Due to COVID- 19 Public Health Emergency
- NMP1L3366, Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting
- NMP1L3369, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
- NMP1L3371, Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-10
- NMP1L3373, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-334, Revision 2
- NMP1L3374, 10 CFR 50.46 Annual Report
- NMP1L3376, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Adopt TSTF-334, Revision 2
- NMP1L3380, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 11 Inoperable
- NMP1L3388, 2020 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2
- NMP1L3389, Annual Radiological Environmental Operating Report
- NMP1L3395, Core Operating Limits Report
- NMP1L3401, (NMP) - Exelon Nuclear Radiological Emergency Plan Document Revisions
- NMP1L3402, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0
- NMP1L3416, General License 30-day Cask Registration Notifications
- NMP1L3419, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, R. E. Ginna, Notification of Closing of Sale of Ownership Interest in Constellation Energy Nuclear Group, LLC
- NMP1L3420, Proposed Alternative to Implement Code Case OMN-28
- NMP1L3421, Independent Spent Fuel Storage Installation, General License 30-day Cask Registration Notifications
- NMP1L3434, 2021 Summary of Regulatory Commitment Changes
- NMP1L3444, CFR 50.46 Annual Report
- NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs
- NMP1L3454, Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps
- NMP1L3457, 2021 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2
- NMP1L3458, Constellation Energy Generation, LLC, Annual Property Insurance Status Report
- NMP1L3459, 2021 Annual Radiological Environmental Operating Report
- NMP1L3462, Independent Spent Fuel Storage Installation, General License 30-day Cask Registration Notifications
- NMP1L3465, Independent Spent Fuel Storage Installation - General License 30-day Cask Registration Notifications
- NMP1L3467, License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage
- NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits
- 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.
- NMP1L3478, Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps
- NMP1L3481, Constellation Energy Generation, LLC, 10 CFR 50, Appendix E - Development of Evacuation Time Estimates
- 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 4b
- NMP1L3484, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors
- NMP1L3485, Proposed Alternative Associated with a Weld Overlay Repair to the Torus
- NMP1L3486, Radiological Emergency Plan Document Revision
- NMP1L3499, CFR 50.46 Annual Report
- NMP1L3513, 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)
- 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)
- NMP1L3516, 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)
- NMP1L3517, Proposed Alternative Associated with a Weld Overlay Repair to the Torus
- NMP1L3518, Proposed Alternative to Utilize Specific Provisions of Code Case N-716-3, Alternative Classification and Examination Requirements Section XI, Division 1
- NMP1L3519, 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)
- NMP1L3520, Supplemental Information for License Amendment Request Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2
- NMP1L3522, Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report
- NMP1L3523, Annual Radioactive Environmental Operating Report
- NMP1L3525, Core Operating Limits Report
- NMP1L3526, Submittal of Emergency Relief Request I5R-14 Concerning a Proposed Alternative Associated with N2E Safe End-to-Nozzle Dissimilar Metal Weld Repair with Laminar Indication
- NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
- 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)
- NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations
- 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 .
- 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 Bases
- NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
- 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)
- NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements
- NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station
- NMP1L3569, CFR 50.46 Annual Report
- NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
- NMP2L2556, Response to Request for Additional Information, License Amendment Request for Maximum Extended Load Line Limit Analysis Plus
- NMP2L2562, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)
- NMP2L2563, License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change
- NMP2L2576, License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
- NMP2L2578, Response to Request for Additional Information -License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change
- NMP2L2579, 2014 Annual Environmental Operating Report
- NMP2L2584, License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy - Nuclear 1 O CFR Part 21 Safety Communication SC05-03
- NMP2L2586, Request for Exemption from 10 CFR Part 50, Appendix a, GDC-56
- NMP2L2588, Nine Mile Point, Unit 2 - Response to Request for Additional Information Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee
- NMP2L2588, Response to Request for Additional Information Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled.
- NMP2L2589, License Amendment Request, Safety Limit Minimum Critical Power Ratio Change, Including Attachment 1, Evaluation of Proposed Changes, Attachment 2, Markup of Technical Specifications Page, and Attachment 4, Non-Proprietary.
- NMP2L2592, Supplemental Information Regarding TSTF-425 License Amendment Request
- NMP2L2595, Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee..
- NMP2L2611, Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
- NMP2L2612, License Amendment Request- Incorporate Previously NRG-Approved TSTF-439 Technical Specifications Changes
- NMP2L2616, Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
- NMP2L2617, Transmittal of 2015 Annual Environmental Operating Report
- NMP2L2620, Submittal of Post Extended Power Uprate Steam Dryer Inspection Results and Long-term Steam Dryer Inspection Plan in Accordance with Operating License Conditions 2.C.(20)(f), 2.C.(20)(g) and 2.C.(20)(h)
- NMP2L2623, Notification of a Deviation from an EPRI Guideline
- NMP2L2634, Emergency License Amendment Request - Proposed Changes to the High Pressure Core Spray System and Reactor Core Isolation Cooling System Actuation Instrumentation Technical Specifications
- NMP2L2639, Supplement to License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy- Nuclear 10 CFR Part 21 Safety Communication SC05-03
- NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
- NMP2L2641, License Amendment Request - Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Revision 0
- NMP2L2643, License Amendment Request-Adoption of TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes
- NMP2L2645, Annual Environmental Operating Report
- NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note
- NMP2L2658, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water
- NMP2L2660, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change
- NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
- NMP2L2664, Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
- NMP2L2667, Supplemental Information No.3 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
- NMP2L2671, Submittal of 2017 Annual Environmental Operating Report
- NMP2L2677, 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 Accident Conditions
- NMP2L2694, Emergency License Amendment Request: One Time Extension to the High Pressure Core Spray Completion Time and Associated Surveillances
- 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.
- NMP2L2697, Submittal of 1O CFR 50.59 Evaluation Summary
- NMP2L2699, License Amendment Request to Revise Technical Specifications Main Steam Isolation Valve Leak Rate
- NMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants
- 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.
- NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879
- NMP2L2713, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Increase Allowable MSIV Leakage Rates
- NMP2L2716, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
- NMP2L2718, Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2
- NMP2L2727, Submittal of 2019 Annual Environmental Operating Report
- NMP2L2729, Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
- NMP2L2739, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2
- NMP2L2742, Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components
- NMP2L2745, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2
- NMP2L2746, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2
- NMP2L2748, Core Operating Limits Report
- NMP2L2749, Responses to Request for Additional Information Questions 17 and 26 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Rev. 2
- NMP2L2754, Responses to Request for Additional Information Questions 27 and 28 to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2
- NMP2L2755, Fourth Inservice Inspection Interval, First Inservice Inspection Period, 2020 Owner'S Activity Report for RFO17 Inservice Examinations
- 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 Control
- NMP2L2765, Submittal of 2020 Annual Environmental Operating Report
- NMP2L2777, Relief Request Associated with Excess Flow Check Valves
- NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
- NMP2L2787, Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves
- NMP2L2789, Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0
- NMP2L2793, Supplemental Information - Relief Request Associated with Excess Flow Check Valves
- NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0
- NMP2L2799, License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators
- NMP2L2805, Annual Environmental Operating Report
- NMP2L2807, Core Operating Limits Report
- NMP2L2811, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2022 Owner'S Activity Report for RFO-18 Inservice Examinations
- NMP2L2823, Supplemental Information for License Amendment Request Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators
- NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications
- NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations
- NMP2L3088, Core Operating Limits Report