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	Issue date	Title	Topic
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 .	4 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 .	Safe Shutdown High winds Reactor Vessel Water Level Mission time Tornado Missile Internal Flooding Probabilistic Risk Assessment Operator Manual Action FLEX Tornado Missile Protection Surveillance Frequency Control Program Scram Discharge Volume Large early release frequency Tornado Missile Risk Evaluator Flooding Focused Evaluation Maintenance Rule Program Offsite Circuit Continuous fire watch Scaffolding
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)	30 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)	Non-Destructive Examination Weld Overlay Coatings Nondestructive Examination VT-2 Liquid penetrant Through-Wall Leakage Dissimilar Metal Weld DM weld
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)	29 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)	Non-Destructive Examination Weld Overlay Coatings Nondestructive Examination VT-2 Liquid penetrant Through-Wall Leakage Dissimilar Metal Weld DM weld
NMP1L3478, Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps	5 August 2022	Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps
RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated	23 February 2022	Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P	Surveillance Frequency Control Program
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	2 February 2022	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	Nondestructive Examination VT-2 Foreign Material Exclusion Through-Wall Leakage
NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0	11 January 2022	Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0	Stroke time Water Inventory Control
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	16 December 2021	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	Reactor Vessel Water Level Ultimate heat sink Stroke time Water Inventory Control Reserve Station Service Transformer Operating Basis Earthquake Qualified Offsite Circuit Surveillance Frequency Control Program Control of Heavy Loads Power Operated Valves Fuel cladding Offsite Circuit Scaffolding
NMP2L2787, Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves	15 November 2021	Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves
JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments	16 September 2021	Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments
NMP2L2773, Company - Response to Request for Additional Information	30 June 2021	Company - Response to Request for Additional Information	Boric Acid
JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments	11 June 2021	Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments
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	4 June 2021	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	Reactor Vessel Water Level Ultimate heat sink Water Inventory Control Surveillance Frequency Control Program Fuel cladding
JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting	20 April 2021	Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting
NMP1L3376, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Adopt TSTF-334, Revision 2	27 January 2021	Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Adopt TSTF-334, Revision 2
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	22 January 2021	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	Maintenance Rule Program
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	7 January 2021	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	Probabilistic Risk Assessment
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	22 October 2020	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	Safe Shutdown Earthquake Maintenance Rule Program
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	2 October 2020	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	Hot Short Safe Shutdown High winds Reactor Vessel Water Level Ultimate heat sink Mission time Internal Flooding Probabilistic Risk Assessment Zebra Mussel Multiple Spurious Operation FLEX Thermoset Scram Discharge Volume Large early release frequency Frazil ice Offsite Circuit
RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568	3 September 2020	Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568
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	28 August 2020	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	Internal Flooding Probabilistic Risk Assessment
ML20188A264	6 July 2020	Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information	Incorporated by reference
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	21 November 2019	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
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	16 October 2019	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	Boric Acid Nondestructive Examination
JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880	4 June 2019	Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880
NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants	1 May 2019	Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants
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	25 February 2019	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 Containm	Surveillance Frequency Control Program
JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880	8 January 2019	Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880	Commercial Grade Dedication Nondestructive Examination
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.	7 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.	Water Inventory Control Surveillance Frequency Control Program MELLLA
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	2 November 2018	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 Pres	Water Inventory Control FLEX Surveillance Frequency Control Program
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, ...	1 October 2018	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, ...	Reactor Vessel Water Level Water Inventory Control Surveillance Frequency Control Program Fuel cladding
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)	17 August 2018	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)
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.	10 May 2018	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.	High winds Earthquake Fuel cladding
RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)	2 May 2018	Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)	Decommissioning Funding Plan Authorized possession limits
ML18025A799	25 January 2018	Response to Request for Additional Information Regarding Generic Letter 2016-01	Aging Management
NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2	27 December 2017	Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2	Reactor Vessel Water Level Water Inventory Control Surveillance Frequency Control Program Recently irradiated fuel
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	3 November 2017	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	Water Inventory Control
NMP1L3180, Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)	18 September 2017	Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)
RS-17-053, Response to Request for Additional Information Regarding Generic Letter 2016-01	27 April 2017	Response to Request for Additional Information Regarding Generic Letter 2016-01	Safe Shutdown Earthquake Earthquake
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	6 April 2017	Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J	Power-Operated Valves Grace period