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CAC:MF9357, Reactor Pressure Vessel Water Inventory Control, Generic Letter 2008-01, Managing Gas Accumulation (Approved, Closed) |
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MONTHYEARNMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 Project stage: Request ML17081A0532017-03-27027 March 2017 Summary of March 9, 2017, Meeting with Exelon Generation Company, LLC, Regarding License Amendment Request to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-542 Project stage: Meeting ML17087A1452017-03-31031 March 2017 Acceptance of Requested Licensing Action Amendment to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control Project stage: Acceptance Review ML17272A0112017-10-10010 October 2017 Request for Additional Information Regarding License Amendment Concerning Reactor Pressure Vessel Water Inventory Control Project stage: RAI 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 Project stage: Response to RAI 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 Project stage: Supplement NMP2L2664, Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22018-01-12012 January 2018 Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 Project stage: Supplement NMP2L2667, Supplemental Information No.3 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22018-02-0606 February 2018 Supplemental Information No.3 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 Project stage: Supplement ML18073A3642018-03-28028 March 2018 Issuance of Amendment No. 168 to Revise Technical Specifications to Adopt TS Traveler Force 542, Revision 2, Reactor Pressure Vessel Water Inventory Control (CAC No. MF9357; EPID L-2017-LLA-0178) Project stage: Approval 2017-03-27
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Category:Letter
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 IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) 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, 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 NMP1L3582, Annual Radioactive Environmental Operating Report2024-05-15015 May 2024 Annual Radioactive Environmental Operating Report IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 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 IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants 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 ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 2024-08-09
[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
[Table view] Category:Technical Specifications
MONTHYEARML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V ML22033A3102022-03-0404 March 2022 Issuance of Amendment No. 190, Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements 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 ML21295A7342021-11-15015 November 2021 Issuance of Amendment No. 187 Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21049A0062021-03-16016 March 2021 Issuance of Amendment No. 245 for Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve ML21077A0142021-03-16016 March 2021 License and Technical Specification Pages for Amendment No. 245, Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20332A1152021-01-29029 January 2021 Issuance of Amendment No. 183 Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems ML19176A0862019-07-30030 July 2019 Issuance of Amendment No. 237 Changes to Containment Oxygen Concentration Requirements ML18344A4522019-01-11011 January 2019 Issuance of Amendment No. 234 Change to Remove Boraflex Credit from Spent Fuel Racks 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. ML18330A0952018-11-30030 November 2018 Correction Duplicate Subparagraph (N) on Technical Specification Page 204 That Occurred in Amendment No. 186 Issued January 25, 2005 RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement ML18032A1772018-03-0606 March 2018 Issuance of Amendment No. 166 to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-522 (CAC No. MF9804; EPID L-2017-LLA-0232) 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 ML17324B1782017-12-21021 December 2017 Issuance of Amendment to Allow Greater Flexibility in Performing Surveillance Testing in Modes 1, 2, or 3 of Emergency Diesel Generators(Cac No. MF9579; EPID L-2017-LLA-0203) ML17152A3202017-06-30030 June 2017 Issuance of Amendments Emergency Plans Emergency Action Level HU1.5 ML17055A4512017-03-0909 March 2017 Issuance of Amendment Partial Length Fuel Rod Burnup ML16088A0532016-04-19019 April 2016 Issuance of Amendment License Amendment Request for Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual ML15352A1642016-03-17017 March 2016 Calvert Cliffs, Units 1 & 2 and Independent Spent Fuel Storage Installation; Nine Mile, Units 1 & 2 and R. E. Ginna - Issuance of Amendments Regarding the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel 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 Manual2016-01-0808 January 2016 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 ML15341A3362016-01-0505 January 2016 Issuance of Amendment Technical Specifications for Safety Limit Minimum Critical Power Ratio 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....2015-12-22022 December 2015 Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements.... ML15317A3072015-11-30030 November 2015 Issuance of Amendment Adoption of Technical Specification Task Force Traveler 425 ML15096A0762015-09-0202 September 2015 Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus ML15223B2502015-08-14014 August 2015 and Nine Mile Point Nuclear Station, Unit No. 2- Copy of License Amendment Nos. 313, 291, 118, and 150 ML15161A3802015-07-30030 July 2015 R. E. Ginna and Nine Mile Point, Unit 2 - Issuance of Amendments Regarding Implementation of Technical Specification Task Force Traveler 523, Generic Letter 2008-01, Managing Gas Accumulation (TAC Nos. MF4405 - MF4409) ML15167A3152015-07-0808 July 2015 Issuance of Amendments Change to TS Requirements Regarding Education and Experience Eligibility Requirements for Licensed Operators ML15110A0082015-05-26026 May 2015 Issuance of Amendment Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change ML15075A1592015-03-17017 March 2015 Correction Letter to Amendment No. 217 Diesel Generator Initiation - Degraded Voltage Time Delay Setting Change (Tac No. MF1022) ML15043A2702015-03-12012 March 2015 Issuance of Amendment Diesel Generator Initiation - Degraded Voltage Time Delay Setting Change ML14126A0032014-06-30030 June 2014 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) ML14057A5542014-05-29029 May 2014 Issuance of Amendment Regarding Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML1233803362012-11-21021 November 2012 License Amendment Request Pursuant to 10 CFR 50.90: Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML1133000472011-12-22022 December 2011 NMP2 EPU - Operating License and Technical Specification Pages ML1133000412011-12-22022 December 2011 Cover Letter - Nine Mile Point Nuclear Station, Unit No. 2 - Issuance of Amendment Extended Power Uprate ML11208C3952011-07-20020 July 2011 License Amendment Requests Pursuant to 10 CFR 50.90: Revisions to the Technical Specifications Design Features Sections to Reflect Transfer of a Portion of Nine Mile Point Nuclear Station Site Real Property ML1018803332010-07-26026 July 2010 Issuance of Amendment No. 206 Modification of TS Section 3.2.7.1 and 4.2.7.1 ML1008904222010-03-22022 March 2010 License Amendment Request Pursuant to 10 CFR 50.90: Revision to Containment Spray System Nozzle Surveillance Frequency ML0926406812009-09-18018 September 2009 License Amendment Request Pursuant to 10 CFR 50.90: Revisions to Primary Coolant System Pressure Isolation Valve Requirements Consistent with Standard Technical Specifications - Tech. Spec. Sections 3.2.7.1 and 4.2.7.1 ML0919504152009-07-0202 July 2009 License Amendment Request to Remove Position Indication for Relief Valves and Safety Valves from Technical Specifications ML0905605222009-02-11011 February 2009 Units, 1 & 2, License Amendment Request for Adoption of TSTF-511-A Rev. 0 Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. 2023-08-30
[Table view] |
Text
Exelon Generation NMP2L2662 December 27, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington
, DC 20555-0001 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 NRG Docket No. 50-41 O 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.90
Subject:
Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control,"
Revision 2
References:
- 1. Letter from J. Barstow (Exelon Generation
- Company, LLC) to U.S. Nuclear Regulatory Commission, "License Amendment Request -Revise Technical Specifications to Adopt TSTF-542,
'Reactor Pressure Vessel Water Inventory Control,'
Revision 2," dated February 28, 2017 2. Letter from M. Marshall (Senior Project Manager, U.S Nuclear Regulatory Commission) to Mr. B. Hanson (Exelon Generation
- Company, LLC), "Nine Mile Point Nuclear Station, Unit 2 -Request for Additional Information Regarding License Amendment Concerning Reactor Pressure Vessel Water Inventory Control (CAC No. MF9357),"
dated October 10, 2017 3. Letter from J. Barstow (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "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 Inventory Control," dated November 3, 2017 4. Public Meeting Announcement, "Meeting with Technical Specifications Task Force (TSTF) RE: TSTF-542, 'Reactor Pressure Vessel Water Inventory Control,'" dated October 27, 2017 By letter dated February 28, 2017 (Reference 1 ), Exelon Generation
- Company, LLC (Exelon) requested to change the Nine Mile Point Nuclear Station, Unit 2 (NMP2) Technical Specifications (TS). The proposed amendment request would revise NMP2 TS by replacing the existing specifications related to Operations with a Potential for Draining the Reactor Vessel with revised requirements for Reactor Pressure Vessel Water Inventory Control to protect / Safety Limit 2.1.1.3. A DD ~/J-U.S. Nuclear Regulatory Commission Supplemental Information TSTF-542, Reactor Pressure Vessel Water Inventory Control Docket No. 50-410 December 27, 2017 Page 2 with revised requirements for Reactor Pressure Vessel Water Inventory Control to protect Safety Limit 2.1.1.3. On October 10, 2017, the U.S. Nuclear Regulatory Commission (NRC) provided a Request for Additional Information (RAI). On November 3, 2017, Exelon submitted to the NRC the RAI response (Reference 3). On October 27, 2017, a public meeting was held by the NRC and the Boiling Water Reactor Owners Group (BWROG) to discuss a proposed TSTF-542 variation affecting BWR/5 and 6 plants. As noted in the NRC Public Meeting Announcement (Reference 4 ), the details of the proposed variation were provided in ADAMS Accession Number ML 17289A902
. Attachment 1 to this letter contains the supplemental information to address the proposed variation provided in ADAMS Accession Number ML 17289A902 and Attachment 2 provides the revised TS and Bases markups. This supplement supersedes the RAI response to Question RAl-1 provided on November 3, 2017 (Reference 3). Also, two additional supplements are provided in Attachment
- 2. First, an editorial error was noted in TSTF-542 affecting Bases Page B 3.3.5.2-8. The statement, "This Function isolates the Group 11 valves," is revised to refer to the Group 5 valves. Second, TS page 3.6.4.3-2, Condition E, was incompletely revised in the original submittal (Reference 1 ). Condition E contains the phrase, " ... or during OPDRVs," that is deleted to meet the intent of TSTF-542, Revision
- 2. See Attachment 2 for the revised TS and Bases markups. 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 supplemental information provided in this letter does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration.
Furthermore
, the supplemental information provided in this letter 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.
With the supplemental information provided in Attachments 1 and 2 to this letter, Exelon requests approval of the proposed amendment by March 1, 2018. The requested approval date supports the implementation of TSTF-542 prior to the start of the refueling outage. Once approved, the amendment shall be implemented no later than the start of NMP2 2018 refueling outage. There are no commitments contained in this response.
If you should have any questions regarding this submittal, please contact Ron Reynolds at 610-765-5247.
U.S. Nuclear Regulatory Commission Supplemental Information TSTF-542, Reactor Pressure Vessel Water Inventory Control Docket No. 50-410 December 27, 2017 Page 3 I declare under penalty of perjury that the foregoing is true and correct.
Executed on the 27th day of December 2017. Jam+/--.) I. Jr--r Director
-Licensing
& Regulatory Affairs Exelon Generation
- Company, LLC Attachment 1: Supplemental Information Attachment 2: Revised Technical Specification Pages and Bases Marked-Up Pages cc: USNRC Region I Regional Administrator USNRC Senior Resident Inspector
-NMP USNRC Project Manager, NRR -NMP A. L. Peterson, NYSERDA w/attachments
" " "
ATTACHMENT 1 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License NPF-69 Docket No. 50-410 SUPPLEMENTAL INFORMATION
*--------------------Supplemental Information TSTF-542, Reactor Pressure Vessel Water Inventory Control Docket No. 50-410 Attachment 1 Page 1 of 2 The Nine Mile Point Unit 2 (NMP2) License Amendment Request (LAR) submittal dated February 28, 2017, for adoption of TSTF-542, is revised to reflect the changes to the Technical Specifications (TS) and Bases as agreed upon between the Boiling Water Reactor Owners Group (BWROG) and the NRC. These changes were discussed during the Public Meeting held on October 27, 2017, with the proposed variation documented in ADAMS Accession Number ML 17289A902
. Subsequently
, a needed change to Surveillance Requirement (SR) 3.5.2.8 was identified for consistency with the proposed variation. See Attachment 2 for revised markups.
Section 2.2, Variations
, of the LAR is revised to add the following
- Table 3.3.5.2-1 is revised to reflect the NMP2 design. Function 3, High Pressure Core Spray (HPCS) System, Function 3.a, "Reactor Vessel Water Level -High, Level 8," and Function 3.e, "Manual initiation
," that appear in TSTF-542 are not included in the proposed Technical Specifications
. This corrects an error in TSTF-542 that affects the BWR/5 and BWR/6 ECCS instrumentation requirements.
The purpose of the manual initiation function is to allow manual actuation of the ECCS subsystem required by TS 3.5.2 to mitigate a draining event. The Reactor Vessel Water Level -High, Level 8 signal prevents overfilling of the reactor vessel into the main steam lines by closing the HPCS injection valves when the water level is above the Level 8 setpoint.
Therefore
, if HPCS is the required ECCS subsystem and the water level is above Level 8, manually actuating Function 3.e will not inject inventory into the reactor vessel. This is not the desired response. If the Level 8 function is retained in Table 3.3.5.2-1, the function would need to be rendered inoperable in order to inject water when above the Level 8 water level. This would not be consistent with including the function in Table 3.3.5.2-1. NMP2 has the capability to manually start the HPCS pump and to open the HPCS injection valve if needed, not utilizing Functions 3.a and 3.e. If desired to inject water into the reactor pressure vessel using the HPCS, the reactor operator can follow procedural steps to take manual control of the pump and injection valve to add inventory.
If the water level is above Level 8, then manual override of the Level 8 function can be performed to allow the HPCS injection valve to be opened. These actions can be performed from the control room and can be accomplished well within the 1-hour minimum drain time limit specified in TS 3.5.2, Condition E. Consequently
, the Function 3.a and 3.e instrumentation functions are not needed to actuate the HPCS subsystem components to mitigate a draining event. The ability to override the HPCS Level 8 isolation is already part of the BWR Emergency Operating Procedures and is practiced during Operator training.
SR 3.5.2.8 is revised to assure that the HPCS manual start capability (including the HPCS Level 8 isolation override feature) is tested.
Supplemental Information TSTF-542, Reactor Pressure Vessel Water Inventory Control Docket No. 50-410 Attachment 1 Page 2 of 2 TS submittal page 3.3.5.2-5 (Table 3.3.5.2-1, page 2 of 2) is revised to delete Functions 3.a. and 3.e. The remaining Functions under 3. High Pressure Core Spray (HPCS) System are renumbered accordingly.
See Attachment 2 for revised markups.
TS submittal page 3.5.2-5 is revised to re-word SR 3.5.2.8 to say, "Verify the required LPCI or LPCS subsystem actuates on a manual initiation signal or the required HPCS subsystem can be manually operated."
See Attachment 2 for revised markups. Bases submittal pages B 3.3.5.2-5 through -8 are revised as follows:
Functions 3.a and 3.e are deleted.
The remaining Functions under 3. High Pressure Core Spray (HPCS) System are renumbered accordingly.
SR 3.5.2.8 description on Bases submittal page B 3.5.2-6 is revised to assure that the HPCS manual start capability (including the HPCS Level 8 isolation override feature) is tested. See Attachment 2 for revised markups.
Also, two additional supplements are provided in this submittal.
First, an editorial error was noted in TSTF-542 affecting Bases Page B 3.3.5.2-8. The statement "This Function isolates the Group 11 valves" is revised to refer to the Group 5 valves. Second, TS page 3.6.4.3-2 was incompletely revised in the original submittal (Reference 1 ). Condition E contains the phrase," ... or during OPDRVs," that is deleted to meet the intent of TSTF-542, Revision
- 2. See Attachment 2 for the revised TS and Bases markups.
ATTACHMENT 2 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License NPF-69 Docket No. 50-410 PROPOSED TECHNICAL SPECIFICATION and BASES MARKED-UP PAGES TS Pages 3.3.5.2-5 3.5.2-5 3.6.4.3-2 Bases Pages B 3.3.5.2-5 thru -8 B 3.5.2-6
- 3. FUNCTION HPCS Pump Discharge Pressure-High (Bypass) (d) HPCS System Flow Rate-Low (Bypass) -JI 4 RHR System Isolation
~-a. Reactor Vessel Water Level-Low, Level 3 5. Reactor Water Cleanup (RWCU) System Isolation
- a. Reactor Vessel Water Level-Low Low, Level 2 RGIG SysteAeiRPV Water Inventory Control Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 2 of 2) RPV Water Inventory Control Instrumentat ion APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 4, 5 4, 5 (c) (c) CONDITIONS REFERENCED REQUIRED FROM CHANNELS PER REQUIRED FUNCTION ACTION A.1 Delete 1 per pump (a) 1 per pump Sul3system (a) 2 in one Trip system 2 in one Trip system F F B B SURVEILLANCE REQUIREMENTS SR 3.3.5.2.2 SR 3.3.5.2.1 SR 3.3.5.2.2 SR 3.3.5.2.1 SR 3.3.5.2.2 SR 3.3.5.2.1 SR 3.3.5.2.2 SR 3.3.5.2.1 SR 3.3.5.2.2 ALLOWABLE VALUE ;,; 220 psig > 580 gpm and s 720 gpm ?: 157.8 inches ?: 101.8 inches (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reactor Pressure Vessel Water Inventory Control." (b) When HPCS is OPERABLE for compliance with LCO 3.5.2, "RPV Water Inventory Control," and aligned to the condensate storage tank. (c) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME. (d) The injection functions of Drywell Pressure-High aAa MaAual IAitiatiaA are\:not required to be OPERABLE with reactor steam dome pressur ess than 600 ps~ JI is Delete NMP2 3.3.5.2-5 Amendment RPV Water Inventory Control 3.5.2 SURVEILLANCE REQUIREMENTS (continued)
SR 3.5.2.6 SR 3.5.2.7 SR 3.5.2.8 NMP2 SURVEILLANCE
N()TE------
Not required to be met for ECCS pumps aligned for shutdown cooling. ()perate the required ECCS injection/spray subsystem through the recirculation line for 10 minutes. Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal. ---------------------
N()TE--------------
Vessel injection/spray may be excluded. Verify the required EGGS il"ljeetiel"IISJ"rey subsystem actuates on a manual initiation signal. \ 1' I FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program I ~LPClorLPCS I or the required HPCS subsystem can be manually operated 3.5.2-5 Amendment 91, 152 ACTIONS CONDITION C. (continued)
D. Two SGT subsystems inoperable in MODE 1, 2, or 3. E. Two SGT subsystems inoperable during movement of recently irradiated fuel assemblies in the secondary containment
'!' t;*isg OP;R¥> t Delete Delete comma and add period NMP2 REQUIRED ACTION C.2.1 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
AWQ G.2.2 li;iitia~e aetiei;i te 6~8f38Fl9 Qi;;!i:;;)~~1,8
. D.1 Enter LCO 3.0.3. E.1 -----------NOTE-----------
LCO 3.0.3 is not applicable.
Suspend movement of recently irradiate d fuel assemblies in the secondary containment. AWQ 3.6.4.3-2 SGT System 3.6.4.3 COMPLETION TIME Immediately lmmeeiately Immediately Immediately
~99FltiFl~89~
Amendment 91, 101, Delete . NMP2 RPV Water Inventory Control Instrumentation B 3.3.5.2 High RPV water le'lel indioates that suffioient oooling water in11entory exists in the reaotor 'lessel suoh that there is no danger to the fuel. Theref.ore
, the Le'lel 8 signal is used to olose the HPCS injeotion 11alve to pre'lent O'lerflow into the main steam lines (MSLs). Reaotor Vessel Water Le'lel High, Le'lel 8 signals for HPCS are initiated from four differential pressure transmitters from the wide range 1.Yater le'lel measurement instrumentation
. One ohannel assooiated with the HPCS System required to be OPeRABLe by LCO 3.5.2 is required to be OPeR/\BLe
. The reaotor Vessel V\f.ater Level High, Le'lel 8 Allowable Value is ohosen to isolate flow from the HPCS System prior to water o'lerflowing into the MSLs. Vessel when manually initiated
. . Pump Suction Pressure
-Low Low pump suction pressure, which is an indication of low level in the CST, indicates the unavailability of an adequate supply of makeup water from this normal source. Normally the suction valves between HPCS and the CST are open and, upon receiving a HPCS initiation signal, water for HPCS injection would be taken from the CST. However, if the pump suction pressure (indicating low water level in the CST) falls below a preselected level for a preselected time, first the suppression pool suction valve automatically opens, and then the CST suction valve automatically closes. This ensures that an adequate supply of makeup water is available to the HPCS pump. To prevent losing suction to the pump, the suction valves are interlocked so that the suppression pool suction valve must be open before the CST suction valve automatically closes. The Functions are implicitly assumed in the accident and transient analyses (which take credit for HPCS) since the analyses assume that the HPCS suction source is the suppression pool. (continued)
B 3.3.5.2-5 Revision O I BASES APPLICABLE SAFETY ANALYSIS, LCO, and APPLICABILITY (continued) 3.b., 3.c. NMP2 RPV Water Inventory Control Instrumentation B 3.3.5.2 Pump Suction Pressure
-Low signals are initiated from two pressure transmitters
. The Pump Suction Pressure
-Low Function Allowable Value is high enough to ensure adequate pump suction head while water is being taken from the CST. The pressure at which the transfer occurs also ensures sufficient volume of water is used by the HPCS pump before the transfer occurs and is analytically determined to prevent the effects of vortexing
. The Pump Suction Pressure
-Timer Function is initiated by a single time delay relay. While the Pump Suction Pressure
-Timer Function is provided to prevent spurious suction source automatic swaps, the Allowable Value is low enough such that the automatic suction swap from the CST to the suppression pool will occur before adequate pump suction head is lost. One channel of the Pump Suction Pressure
-Low Function are only required to be OPERABLE when HPCS is required to be OPERABLE to ensure that no single instrument failure can preclude HPCS swap to suppression pool source. In addition, one channel of the Pump Suction Pressure
-Timer Function is only required to be OPERABLE when HPCS is required to be OPERABLE.
Thus, the Functions are required to be OPERABLE in MODES 1, 2, and 3. In MODES 4 and 5, the Functions are required to be OPERABLE only when HPCS is required to be OPERABLE to fulfill the requirements of LCO 3.5.2, HPCS is aligned to the CST, and the CST water level is not within the limits of SR 3.5.2.2. With CST water level within limits, a sufficient supply of water exists for injection to minimize the consequences of a vessel draindown event. Refer to LCO 3.5.1 and LCO 3.5.2 for HPCS Applicability Bases . . , .. HPCS Pump Discharge Pressure
-High (Bypass) and HPCS System Flow Rate -Low {Bypass)
The minimum flow instruments are provided to protect the HPCS pump from overheating when the pump is operating and the associated injection valve is not fully open. The minimum flow line valve is opened when low flow and high pump discharge pressure are ( continued)
B 3.3.5.2-6 Revision O I BASES APPLICABLE SAFETY ANALYSIS, LCO, and APPLICABILITY (continued)
NMP2 RPV Water Inventory Control Instrumentation B 3.3.5.2 sensed, and the valve is automatically closed when the flow rate is adequate to protect the pump or the discharge pressure is low (indicating the HPCS pump is not operating)
. The HPCS System Flow Rate -Low (Bypass) and HPCS Pump Discharge Pressure
-High (Bypass)
Functions are assumed to be OPERABLE and capable of closing the minimum flow valve to ensure that the ECCS flow assumed during the transients and accidents analyzed in References 1, 2, and 3 are met. The core cooling function of the ECCS, along with the scram action of the RPS, ensures that the fuel peak cladding temperature remains below the limits of 10 CFR 50.46. One differential pressure transmitter is used to detect the HPCS Systems' flow rate. The logic is arranged such that the transmitter causes the minimum flow valve to open, provided the HPCS pump discharge pressure, sensed by another transmitter
, is high enough (indicating the pump is operating)
. The logic will close the minimum flow valve once the closure setpoint is exceeded. (The valve will also close upon HPCS pump discharge pressure decreasing below the setpoint.)
The HPCS System Flow Rate -Low and HPCS Pump Discharge Pressure
-High Allowable Value is high enough to ensure that pump flow rate is sufficient to protect the pump, yet low enough to ensure that the closure of the minimum flow valve is initiated to allow full flow into the core. The HPCS Pump Discharge Pressure
-High Allowable Value is set high enough to ensure that the valve will not be open when the pump is not operating
. One channel of each Function associated with one pump is required to be OPERABLE when HPCS is required to be OPERABLE by LCO 3.5.2 in MODES 4 and 5. 3.e. Manual Initiation The Manual Initiation switoh and push button ohannels introduoe a signal into the HPGS logio to pro\*ide manual initiation oapability and is redundant to the automatio proteotive instrumentation.
There is one switoh and push button (with two ohannels) for the HPCS System. One ohannel of the Manual Initiation Funotion is only required to be OPER/\8LE in MODES 4 and 5 when the assooiated EGGS subsystem is required to be OPER/\8LE per LCO 3.5.2. B 3.3.5.2-7 Revision O I BASES APPLICABLE SAFETY ANALYSIS, LCO, and APPLICABILITY
( continued)
NMP2 RPV Water Inventory Control Instrumentation B 3.3.5.2 RHR System Isolation 4.a -Reactor Vessel Water Level -Low. Level 3 The definition of DRAIN TIME allows crediting the closing of penetration flow paths that are capable of being automatically isolated by RPV water level isolation instrumentation prior to the RPV water level being equal to the TAF. The Reactor Vessel Water Level -Low, Level 3 Function is only required to be OPERABLE when automatic isolation of the associated RHR penetration flow path is credited in calculating DRAIN TIME. Reactor Vessel Water Level -Low, Level 3 signals are initiated from two differential pressure transmitters (two per trip system) that sense the difference between the pressure due to a constant column of water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel. While four channels (two channels per trip system) of the Reactor Vessel Water Level -Low, Level 3 Function are available
, only two channels (all in the same trip system) are required to be OPERABLE. The Reactor Vessel Water Level -Low, Level 3 Allowable Value was chosen to be the same as the RPS Reactor Vessel Water Level -Low, Level 3 Allowable Value (LCO 3.3.1.1 ), since the capability to cool the fuel may be threatened
. This Function isolates the Group ¥valve--;:
Reactor Water Cleanup (RWCU) System Isolation 5.a -Reactor Vessel Water level -Low Low, Level 2 The definition of DRAIN TIME allows crediting the closing of penetration flow paths that are capable of being automatically isolated by RPV water level isolation instrumentation prior to the RPV water level being equal to the TAF. The Reactor Vessel Water Level -Low Low, Level 2 Function associated with RWCU System isolation may be credited for automatic isolation of penetration flow paths associated with the RWCU System. (continued)
B 3.3.5.2-8 Revision O I BASES SURVEILLANCE REQUIREMENTS RPV Water Inventory Control~
St;iwt*1ewr1 B 3.5.2 SR 3.5.2.4-§ (seRtiRweEil)
Verifying that the required ECCS injection/spray subsystem can be manually started and operate for at least 10 minutes demonstrates that the subsystem is available to mitigate a draining event. Testing the ECCS injection/spray subsystem through the recirculat ion line is necessary to avoid overfilling the refueling cavity. The minimum operating time of 10 minutes was based on engineering judgment.
~eeewse ef tt;ie lew i,resswre er1*1 lew temi,eretwre eer1*1itier1s iFl MQgl!!s 4 eR*1 §, sw~ieieRt tiFRe will lile eveileele te FReRwelly eli~R er,;ie iRitiete bPCI swlils','steFR ei,eretieR te ~re1w1iEile eere eeeliR~ ~rier te i,estwlet0*1 fwel wr1e0vePf
. Tt;iis will er1swr0 e*1e*lwete eere ee0lir1~
if er1 ir1e*1vert0r1t vessel *1reir,;i*10wr1 st;iewl*1 eeewr. Tt;;ie Swr1w1eiller,;iee is FReEilifieEil B',' a ~lets wt;;iiet;;i S'KSFR~ts S','SteFR 1;1er;it flew i,ett;is ei,0r1e*1 wr1*1er e*1mir1istretive e0r1trnl.
Tt;ie e*1mir1istretive eeRtrnl st;iewl*1 ee ~r9eeEilwrelii!!eEil eR*1 iRelwele stetieR a *1e*1ieete*1 iR*1ivi*1wel et tt;ie systeFR ver;it flew i,ett;;i wt;ie is iR eer,;itir,;iwe1s1s eeFRFRWRieetieR witt;;i tt;;ie ei,ereters iR tt;;ie eer;itrel reeFR. Tt;;iis iR*1iviEilwel will l;ieve a metl;ie*1 te rei,ielly elese tl;ie system ver1t flew i,ett;i if Eilireete*1
. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.5.2.7 Verifying that each valve credited for automatically isolating a .---------------.
penetration flow path actuates to the isolation position on an Insert A The HPCS System is verified to start manually from a standby configuration
, and includes the ability to override the RPV Level 8 injection valve isolation.
actual or simulated RPV water level isolation signal is required to prevent RPV water inventory from dropping below the TAF should an unexpected draining event occur. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. SR 3.5.2.8 The required E CS subsystem is required to actuate on a manual initiaf n signal. This Surveillance verifies that a -------I[pcfl
~
manual initi ion signal will cause the required~~
c.....::..:..J NMP2 subsystem
, PCS System, or f9pcg gystem to start and operate as designed, including pump startup and actuation of all automatic valves to their required positions
. The Surveillance Frequency is controlled under the urveillance Frequency Control Program. Insert A This SR is modified by a Note that excludes vessel injection/spray during the Surveillance
. Since all active B 3.5.2-6 Revision 0, 43 (A150), 44 (A 152)