Letter Sequence Response to RAI |
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CAC:MF5364, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B (Approved, Closed) |
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Category:Letter type:NMP
MONTHYEARNMP1L3601, 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 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 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 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 NMP1L3582, Annual Radioactive Environmental Operating Report2024-05-15015 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 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 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 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report 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 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 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) 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 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 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 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 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 . 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 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 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) NMP1L3523, Annual Radioactive Environmental Operating Report2023-05-12012 May 2023 Annual Radioactive Environmental Operating Report NMP1L3522, Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report2023-04-30030 April 2023 Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report NMP1L3525, Core Operating Limits Report2023-04-19019 April 2023 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 Indication2023-04-13013 April 2023 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 NMP1L3520, Supplemental Information for License Amendment Request Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 22023-04-0404 April 2023 Supplemental Information for License Amendment Request Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2 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)2023-03-30030 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) 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)2023-03-29029 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) NMP1L3517, Proposed Alternative Associated with a Weld Overlay Repair to the Torus2023-03-29029 March 2023 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 12023-03-29029 March 2023 Proposed Alternative to Utilize Specific Provisions of Code Case N-716-3, Alternative Classification and Examination Requirements Section XI, Division 1 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) 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)2023-03-24024 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) NMP1L3499, CFR 50.46 Annual Report2023-01-27027 January 2023 CFR 50.46 Annual Report 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 NMP1L3486, Radiological Emergency Plan Document Revision2022-12-15015 December 2022 Radiological Emergency Plan Document Revision 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 NMP1L3485, Proposed Alternative Associated with a Weld Overlay Repair to the Torus2022-12-0808 December 2022 Proposed Alternative Associated with a Weld Overlay Repair to the Torus NMP2L2823, Supplemental Information for License Amendment Request Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators2022-10-28028 October 2022 Supplemental Information for License Amendment Request Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators NMP1L3481, Constellation Energy Generation, LLC, 10 CFR 50, Appendix E - Development of Evacuation Time Estimates2022-09-15015 September 2022 Constellation Energy Generation, LLC, 10 CFR 50, Appendix E - Development of Evacuation Time Estimates 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. NMP1L3478, Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps2022-08-0505 August 2022 Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps 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 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 NMP1L3465, Independent Spent Fuel Storage Installation - General License 30-day Cask Registration Notifications2022-06-17017 June 2022 Independent Spent Fuel Storage Installation - General License 30-day Cask Registration Notifications NMP1L3462, Independent Spent Fuel Storage Installation, General License 30-day Cask Registration Notifications2022-06-0909 June 2022 Independent Spent Fuel Storage Installation, General License 30-day Cask Registration Notifications 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 NMP2L2811, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2022 Owner'S Activity Report for RFO-18 Inservice Examinations2022-05-13013 May 2022 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2022 Owner'S Activity Report for RFO-18 Inservice Examinations NMP1L3459, 2021 Annual Radiological Environmental Operating Report2022-05-0808 May 2022 2021 Annual Radiological Environmental Operating Report 2024-07-31
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24222A6772024-08-0909 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 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 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 . 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)2023-03-30030 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) 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)2023-03-29029 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) NMP1L3478, Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps2022-08-0505 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 Actuated2022-02-23023 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 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 Repairs2022-02-0202 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 NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 02022-01-11011 January 2022 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0 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 02021-12-16016 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 NMP2L2787, Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves2021-11-15015 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 Amendments2021-09-16016 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 Information2021-06-30030 June 2021 Company - Response to Request for Additional Information JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 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 02021-06-0404 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 JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 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 22021-01-27027 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 22021-01-22022 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 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 22021-01-0707 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 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. 22020-10-22022 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 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 22020-10-0202 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 RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 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 Components2020-08-28028 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 ML20188A2642020-07-0606 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 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 Rates2019-11-21021 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-8792019-10-16016 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 JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 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 Plants2019-05-0101 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 Contain2019-02-25025 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 JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 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. 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 Pre2018-11-0202 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 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, ...2018-10-0101 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, ... 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)2018-08-17017 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.2018-05-10010 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. RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) ML18025A7992018-01-25025 January 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-27027 December 2017 Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 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 Water2017-11-0303 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 NMP1L3180, Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)2017-09-18018 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 2016-012017-04-27027 April 2017 Response to Request for Additional Information Regarding Generic Letter 2016-01 NMP1L3146, Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J2017-04-0606 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 RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography RS-17-027, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-03-10010 March 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal ML17037A2652017-02-0606 February 2017 Response to Request for Information Concerning Regional Meteorological Conditions Characterizing Atmospheric Transport Processes within 50 Miles of the Plant RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure ML16131A6542016-05-0404 May 2016 Response to a Question Raised During the Audit ML16131A6552016-05-0404 May 2016 White Paper Prepared in Response to a Question Raised During the Audit 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 Manual2016-03-21021 March 2016 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 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....2016-01-25025 January 2016 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.... 2024-08-09
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Exelon Generation 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.90 NMP2L2588 July 1O, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 NRC Docket No. 50-410
Subject:
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 Program (Adoption of TSTF-425, Revision 3)."
References:
- 1. Letter from J. Barstow (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "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),"
dated November 19, 2014.
- 2. Email from Brenda Mozafari (Licensing Project Manager, U.S. Nuclear Regulatory Commission) to Ronnie Reynolds and Enrique Villar (Exelon Generation Company, LLC) Draft Request for additional information regarding TSTF-425, Rev. 3," dated June 16, 2015.
This letter responds to the U.S. Nuclear Regulatory Commission request for additional information (Reference 2) requesting Exelon Generation Company, LLC (Exelon) provide additional information regarding the License Amendment Request (LAR) to modify the Nine Mile Point Unit 2 (NMP2) Technical Specifications (TS) (Reference 1). The proposed amendment request would modify NMP2 TS by relocating specific surveillance frequencies
Response to Request for Additional Information Adoption of TSTF-425, Revision 3 July 10, 2015 Page 2 to a licensee-controlled program with the implementation of Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies." to this letter contains the NRC's request for additional information immediately followed by Exelon's response.
Exelon has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration provided to the NRC in Reference 1.
The additional information provided in this response does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. Furthermore, the additional information provided in this response does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
There are no regulatory commitments contained in this letter.
If you should have any questions regarding this submittal, please contact Enrique Villar at 610-765-5736.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 101h day of July 2015.
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James Barstow ~ - U.
Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachment 1: Response to Request for Additional Information cc: USNRC Region I Regional Administrator w/attachments USN RC Senior Resident Inspector - NMP USNRC Project Manager, NRA - NMP A. L. Peterson, NYSERDA
ATTACHMENT 1 Response to Request for Additional Information to Support Review of Nine Mile Point Nuclear Station, Unit 2 Adoption of Technical Specification Task Force-425 Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TAC No. MF5364)
Response to Request for Additional Information Attachment 1 Adoption of TSTF-425, Revision 3 Page 1 of 7 PRA RAI 1 In Attachment 2, Section 2.5 "References," of the License Amendment Request (LAR), the licensee provides references that suggest the July 2009 peer review was performed using ASME RA-Sc-2007, "Addenda to ASME RA-S-2002 Standard for Probabilistic Risk Assessment [PRA] for Nuclear Power Plant Applications." The staff would like to clarify that Regulatory Guide 1.200, Revision 2, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities" (ML090410014), provides clarification to ASME/ANS RA-Sa-2009 on providing a technically adequate PAA. Furthermore, consistent with the information provided in Regulatory Issue Summary (RIS) 2007-06 (ADAMS Accession No. ML070650428), "Regulatory Guide 1.200 Implementation," the NRG staff will use Revision 2 of RG 1.200 (ADAMS Accession No. ML090410014) to assess technical adequacy of the PRA used to support risk-informed applications received after March 2010. If the licensee did not use ASME/ANS RA-Sa-2009, "Addenda to ASME/ANS RA-S-2008 Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications,"
then they would need to perform a gap analysis for the differences in revisions and provide the applicable Facts and Observations (F&Os) of that gap analysis.
- a. Explain whether the peer review was performed to ASME/ANS RA-Sa-2009 as clarified by AG 1.200 Revision 2.
Exelon Response to PRA RAI 1 Yes. The Nine Mile Point Nuclear Station Unit 2 (NMP2) Peer Review Team used ASME/ANS RA-Sa-2009 as clarified by RG 1.200 Revision 2.
PRA-RAI 2 The licensee stated that its PRA model update to meet Regulatory Guide (AG) 1.200 was completed and peer reviewed in July 2009. The licensee further stated that the peer review resulted in "18 findings which did not meeting Capability Category (CC) II and 34 suggestions that met CCII." The licensee also provided Table 2-1 which lists six open findings that have yet to be resolved per the licensee's update process. As discussed in AG 1.200, Revision 2, Regulatory Position 4.2, the licensee should provide discussion regarding the resolution of the peer review findings and observations that are applicable to the parts of the PRA required for the application.
- a. If the July 2009 peer review was performed using ASME/ANS RA-Sa-2009, then provide all the applicable findings and suggestions resulting from the 2009 peer review, their disposition, and the potential impact on the Risk-Informed Surveillance Test Interval (RI STI) application. If the peer review was not performed using ASME/ANS RA-Sa-2009, then provide the applicable findings and suggestions resulting from the gap analysis as mentioned in PAA RAI 1, their disposition, and the potential impact on the RI STI application.
Response to Request for Additional Information Attachment 1 Adoption of TSTF-425, Revision 3 Page 2 of 7 Exelon Response to PRA RAI 2 NMP2 Probabilistic Risk Assessment (PRA) model periodic updated is being performed in 2015 per the Exelon Risk Management Training and Requirements Manuals and procedures. The resolutions of the Open Findings and Suggestions below describe actions performed during the 2015 periodic update and documented in the updated PRA notebooks per the Exelon PRA update process.
The following Table shows the applicable Findings and Suggestions from the Peer Review that are applicable to support a Risk Informed Surveillance Frequency Control Program at NMP2:
Response to Request for Additional Information Attachment 1 Adoption of TSTF-425, Revision 3 Page 3 of 7 Finding/ Assoc. Basis for Possible F&O I F&O Description I NMPZ Action/Response Comment Sugestion SR Significance Resolution URE 472: Demands from causes other than surveillance tests were not included in the OPEN collection of plant-specific Include demands Insignificant Impact - Defer for data.
from the four consideration during next major (This F&O originated from SR causes listed in the update. DA-CG)
Demands from causes other than SR. Perhaps use It was looked at during unit 1 SR requires oil surveillance tests were not included in MSPI estimates for update and considered again during URE 472 Resolution : Appendix DA-CG types of demands 1-1 I the collection of plant-specific data.
DA-C7 be counted or MSPI components unit 2 update. It is a little c of the Data Notebook because that conservative and not considered discusses the Plant-Specific estimated.
(This F&O originated from SR DA-CG) program includes significant to estimate using Unavailability Assessment. It al/demands surveillance procedures. Note that includes plant-specific (except post MSPI no longer counts actual demands on the basis of:
maintenance test). events; they estimates the same A) Surveillance Tests way the PRA Group does. B) Maintenance Tests C) Operationa I Demand s URE 472 can be closed .
P. 2-7 of the DA Notebook states that a Perform Bayesian Bayesian analysis was not done when update when data there are no plant-specific failures. This is is available and unacceptable for Category II or Category zero plant-specific Ill. Bayesian updates for events failures are CLOSED with zero plant specific failures It is not observed, or, The discussion justifying not performing Section 2 of DA Notebook and will be performed. This w ill acceptable to skip alternatively, such updates on p. 2-G and 2-7 of the DA Model were updated with Bayesian continue to be performed performing a show that it is I Notebook is misleading because of the analysis for zero events down to going forward per Exelon Best 2-5 DA-Dl Bayesian update unlikely to get the very small failure probabilities involved in failure rates on the order of lE-3. Practices, Procedures and Test when zero plant- required number the example given. The conservatism of no performing and Requirements Manuals.
specific failures of demands to this update for lower failure rates is Specifically, Exelon Best are observed. significantly Based on NUREG/CR-G928 parameters for shown to be minor. Practice, BP-OOG, is used for change the failure distributions with as few as 200 to 1000 PRA data analysis.
probability for demands, the posterior mean could drop specific equipment by a factor of 2 showing zero I , failures.
(This F&O originated from SR DA-Dl)
Response to Request for Additional Information Attachment 1 Adoption of TSTF-425, Revision 3 Page 4 of 7 F&O I F&O Description Finding/
Sugestion Assoc.
SR Basis for Significance I Possible Resolution I NMP2 Action/Response I Comment A critical test of the posterior that is suggested in this Supporting Requirement is:
(c) examination of inconsistencies between the prior distribution and the plant-specific evidence to confirm that they are appropriate. I CLOSED Consistency Section 2. 7 of DA Notebook There is at least one case in which data is between the updated to include test of key Exelon Best Practice BP-OOG inconsistent--MOV (lake) fails to open. plant-specific data Perform distributions with documentation provides guidance for There were Gfailures in 150 demands. and the prior was recommended of methodology. A few treatment of posterior 2-G I The prior from NUREG/CR-G928 for MOV DA-D4 not evaluated. A consistency distributions were identified as Bayesian update results that FTO/C has a mean of 1.07 E-3. The representative analyses for all potentially inconsistent (prior are inconsistent with plant-method from NUREG/CR-G823, Section example of such data. versus posterior and plant data). As specific performance.
G.2.3.5 & G.3.3.4 describe a method for an inconsistency is a result, the uncertainty in the prior consistency evaluation that suggests that provided. distribution was increased to be greater than or equal to 2 failures would more representative of plant data.
be inconsistent and that another prior should be used.
There is no documentation of any NMP-2 analysis like this.
(This F&O originated from SR DA-D4)
-1 OPEN - Insignificant URE 474: Routine system Wait for plant reliability model alignments contributing to development. initiating event frequencies are Routine alignments are already not included. (This F&O included in the average initiating originated from SR IE-AG) event frequency development. In Include routine system Include routine addition, the addition of support alignments in the calculation Routine system alignments contributing system alignments system initiating event fault trees of initiating event frequencies, to initiating event frequencies are not I Does not meet IE- in the calculation to the model (see F&O 2-16 and 4- where applicable.
5-2 I included. IE-AG A6Catll of initiating event 4) adds some important alignments requirements. Resolution for URE 474: SR IE-frequencies, for these systems. It would be a (This F&O originated from SR IE-AG) I where applicable. significant effor to add the type of A6 Capability Category II states: When performing the factors that are typically reserved for EOOS risk managment modeling systematic evaluation required such as 1/2 scram testing etc. This in IE-AS, INCLUDE initiating will have to wait until a plant events resulting from multiple reliability program is developed failures, if the equipment (e.g., scram risk).
failures result from a common cause, and from routine
Response to Request for Additional Information Attachment 1 Adoption of TSTF-425, Revision 3 Page 5 of 7 Finding/ Assoc. Basis for Possible F&O I F&O Description NMPZ Action/Response Comment Sugestion SR Significance Resolution system alignments.
Section 2.5.2 of the Initiating Events Notebook discusses the routine system alignment for each special initiating event.
The system fault trees developed for special initiating events include maintenance and alignment gates. The fault trees are used to obtain a system failure rate, which includes input from any maintenance and alignment gates in the system model.
Table 3-10 lists system fault tree initiator values.
Section 2.5.2.6 discusses multiple failures for each special initiating event due to the potential for common cause effects.
Based on the requirements identified in SR IE-AG, the systematic evaluation performed considered routine system alignments, and common cause failures. The routine system alignments and common cause failures are included in the system fault trees developed, and discussion is provided in the Initiating Events Notebook.
Therefore, the requirements of the F&O and URE 474 have been satisfied, and URE 474 can be closed.
Response to Request for Additional Information Attachment 1 Adoption of TSTF-425, Revision 3 Page 6 of 7 Finding/ Assoc. Basis for Possible F&O F&O Description NMPZ Action/Response Comment Sugestion SR Significance Resolution The emergency diesel generator output circuit breaker is modeled separate from the emergency diesel generator in the Eliminate the CLOSED PRA, while it is included in the emergency This is an isolated circuit breaker EOG output breaker basic event set Treatment of the EOG output diesel generator boundary in NU REG/CR- error associated fram the made/, or DA-Cl to 0.0 in model. As a result circuit breakers and the EDG 1-3 6928 (which provides the prior). This Suggestion with this SR and change its failure SY-A8 documentation in several component boundary is being results in over counting of circuit breaker the result is probability to zero notebooks were updated (SY.00, maintained as stated.
failures, which is significant for the FTLR conservative. (to prevent double SY.01 and DA Notebooks).
failure mode. counting).
(This F70 originated from SR DA-Cl)
- p. 2-7 of the DA Notebook states that a This is a documentation error.
Bayesian analysis was not done when See resolution above for 2-5 Please state there are no plant-specific failures. regarding current and future correctly what CLOSED treatment of zero failures.
Error in was done with 2-4 An exception to this statement was Suggestion DA-Dl This error was corrected (also see documentation. situations with found-- Div I & Div II emergency diesel F&O 2-5).
zera plant-specific generator failure to start.
failures .
(This F&O originated from SR DA-Dl)
Response to Request for Additional Information Attachment 1 Adoption of TSTF-425, Revision 3 Page 7 of 7 PRA RAI 3 The LAR does not provide a discussion or description of any low-power or shutdown events. A qualitative analysis of shutdown events is acceptable, as presented in the NRG-endorsed document NEI 04-10, Revision 1. Step 10 of Section 4.0 of NEI 04-10, Revision 1, provides guidance on the initial assessment of Internal Events, External Events, and Shutdown Events. Describe how shutdown events will be assessed as part of the Nine Mile Point, Unit 2, Surveillance Frequency Control Program.
Exelon Response to PRA RAI 3 Changes to surveillance frequencies under the Surveillance Frequency Control Program will consider external, lower power and shutdown events in accordance with NEI 04-10, Revision 1, Section 4.0, Step 10.