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Category:Letter type:NMP
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation 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 NMP1L3457, 2021 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 22022-04-30030 April 2022 2021 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2 NMP2L2805, Annual Environmental Operating Report2022-04-23023 April 2022 Annual Environmental Operating Report NMP2L2807, Core Operating Limits Report2022-04-0707 April 2022 Core Operating Limits Report NMP1L3458, Constellation Energy Generation, LLC, Annual Property Insurance Status Report2022-04-0101 April 2022 Constellation Energy Generation, LLC, Annual Property Insurance Status Report NMP1L3454, Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps2022-03-0202 March 2022 Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps 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 NMP1L3444, CFR 50.46 Annual Report2022-01-27027 January 2022 CFR 50.46 Annual Report 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 NMP2L2793, Supplemental Information - Relief Request Associated with Excess Flow Check Valves2021-12-17017 December 2021 Supplemental Information - Relief Request Associated with Excess Flow Check Valves NMP2L2789, Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 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 2024-02-01
[Table view] Category:Technical Specification
MONTHYEARRS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. ML22292A1312022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Technical Specification Bases, Rev. 69 RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration NMP1L3477, License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise.2022-08-12012 August 2022 License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise. NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-30030 September 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements NMP2L2762, License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2021-05-26026 May 2021 License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability NMP2L2718, Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22019-12-12012 December 2019 Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls NMP2L2693, Technical Specification Bases, Rev. 572018-10-24024 October 2018 Technical Specification Bases, Rev. 57 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 NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note2017-08-22022 August 2017 License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 ML16309A4002016-10-24024 October 2016 Revision 47 to Technical Specification Bases, List of Effective Pages ML16309A4022016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B2.0, Safety Limits (Sls) ML16309A4032016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.0, Limiting Condition for Operation (LCO) Applicability ML16309A4012016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Table of Contents ML16309A4082016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.5, Emergency Core Cooling Systems (ECCS) and Reactor Core Isolation Cooling (RCIC) System ML16309A4132016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.9, Refueling Operations ML16309A4052016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.2, Power Distribution Limits ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. NMP1L3070, License Amendment Request - Reactivity Anomalies Surveillance2016-03-18018 March 2016 License Amendment Request - Reactivity Anomalies Surveillance NMP2L2592, Supplemental Information Regarding TSTF-425 License Amendment Request2015-09-24024 September 2015 Supplemental Information Regarding TSTF-425 License Amendment Request NMP1L3027, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)2015-05-12012 May 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) ML15089A2312015-03-26026 March 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) NMP1L3010, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)2015-03-26026 March 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) NMP2L2576, License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2015-03-23023 March 2015 License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual NMP2L2563, License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change2014-11-17017 November 2014 License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change ML14191A2552014-07-10010 July 2014 Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML12156A3632012-06-0101 June 2012 Emergency License Amendment Request Pursuant to 10 CFR 50.90: Revision of the Main Steam Isolation Valve Allowable Leakage Rate Limit ML11306A2982011-10-27027 October 2011 Submittal of Revision 22 to the Final Safety Analysis Report (Updated), 10 CFR 50.59 Evaluation Summary Report, Technical Specifications Bases Changes, and Report Consistent with 10 CFR 54.37(b) ML11214A2142011-07-25025 July 2011 License Amendment Request, Extension of the Completion Time for Inoperable Diesel Generator - Response to NRC Request for Additional Information ML1109602832011-03-30030 March 2011 License Amendment Request Pursuant to 10 CFR 50.90: Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage ... ML0935000902009-12-0909 December 2009 License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery - Technical Specification 3.8.4, DC Sources - Operating ML0931602572009-10-26026 October 2009 Submittal of Revision 21 to the Final Safety Analysis Report (Updated), 10 CFR 50.59 Evaluation Summary Report, Technical Specifications Bases Changes, and Report Consistent with 10 CFR 54.37(b) ML0907802502009-03-0909 March 2009 Submittal of Amendment Request for Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency ML0906403012009-03-0303 March 2009 License Amendment Request Pursuant to 10 CFR 50.90: Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML0827502992008-09-29029 September 2008 Technical Specifications ML0802501622008-01-24024 January 2008 Response to NRC Request for Additional Information Regarding Nine Mile Point Nuclear Station, Unit No. 1, Revision of Rod Worth Minimizer Limiting Condition for Operation During Startup ML0726401032007-09-19019 September 2007 License Amendment Request for Adoption of TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities. ML0721906052007-07-30030 July 2007 Application for Technical Specification Change TSTF-477, Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process ML0721205922007-07-23023 July 2007 Application for Technical Specification Improvement to Adopt TSTF-476, Revison 1, Improved BPWS Control Rod Insertion Process (NEDO-33091), Using the Consolidated Line Item Improvement ML0721205872007-07-23023 July 2007 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Rod Worth Minimizer Limiting Condition for Operation During Startup - Technical Specification Section 3.1.1.b ML0720504232007-07-12012 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0720504742007-07-12012 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0707800592007-03-15015 March 2007 Technical Specification 4.1.1 Regarding Control Rod System Surveillance Requirements ML0630406022006-10-19019 October 2006 License Amendment Request Pursuant to 10 CFR 50.90: Revision to Control Rod System Surveillance Requirements - Technical Specification 4.1.1 2023-05-25
[Table view] Category:Amendment
MONTHYEARRS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-30030 September 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability NMP2L2718, Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22019-12-12012 December 2019 Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls 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 NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note2017-08-22022 August 2017 License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP1L3027, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)2015-05-12012 May 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) NMP2L2576, License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2015-03-23023 March 2015 License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual NMP2L2563, License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change2014-11-17017 November 2014 License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change ML14191A2552014-07-10010 July 2014 Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML1109602832011-03-30030 March 2011 License Amendment Request Pursuant to 10 CFR 50.90: Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage ... ML0935000902009-12-0909 December 2009 License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery - Technical Specification 3.8.4, DC Sources - Operating ML0907802502009-03-0909 March 2009 Submittal of Amendment Request for Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency ML0906403012009-03-0303 March 2009 License Amendment Request Pursuant to 10 CFR 50.90: Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML0827502992008-09-29029 September 2008 Technical Specifications ML0720504742007-07-12012 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0707800592007-03-15015 March 2007 Technical Specification 4.1.1 Regarding Control Rod System Surveillance Requirements ML0536202882005-12-16016 December 2005 License Amendment Request: Proposed Changes to Technical Specification 4.1.4 Regarding Core Spray Instrumentation ML0511100732005-04-19019 April 2005 Tech Spec Pages for Amendment 115 and 188 Reporting Requirements for Annual Radiological Environmental Operating Report ML0510204002005-04-0101 April 2005 License Amendment Request Pursuant to 1O CFR 50.90: Request for Amendment to Extend Completion Time for Emergency Uninterruptible Power Supply Inverters ML0503304712005-01-24024 January 2005 Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports ML0424003162004-08-17017 August 2004 Unit I, License Amendment Request Pursuant to 10 CFR 50.90: Addition of 24 Hours for Restoration of Primary Containment Oxygen Concentration ML0421103812004-07-16016 July 2004 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Intermediate Range Monitor Surveillance Frequency and Relocation of Selected Instrumentation Requirements to a License-Controlled Document ML0403302112004-01-27027 January 2004 TS Amendment Pages for License No. NPF-069 ML0330305992003-10-27027 October 2003 TS Pages Amendment 183 ML0324608472003-08-15015 August 2003 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Reactor Pressure Vessel Pressure-Temperature Limits ML0233807302002-11-22022 November 2002 Facility Operating License DPR-63, License Amendment Request: Technical Specifications Section 6.0, Administrative Controls - Response to RA Information TAC No. MB2441 ML0229603382002-10-0707 October 2002 Application for Technical Specification Change Regarding Missed Surveillances Using the Consolidated Line Item Improvement Process ML0217101682002-06-0707 June 2002 Application for Technical Specification Improvement to Eliminate the Requirements for the Post Accident Sampling System Using the Consolidated Line Item Improvement Process ML0207305992002-03-13013 March 2002 Technical Specifications, Issuance of Amendment Safety Limit Minimum Critical Power Ratio (Tac No. MB3327) ML0206302682002-03-0101 March 2002 Technical Specifications for Amendment No. 103 ML0204301512002-02-11011 February 2002 Issuance of Amendment Ventilation Requirements During Irradiated Fuel Handling ML18018B0461978-03-22022 March 1978 Letter Transmitting an Application for Amendment to Appendix a of the Operating License ML17037C4331977-08-0808 August 1977 Letter Regarding Surveillance Requirements and Limiting Conditions for Operations and Requesting an Application for Amendment to the Operating License That Will Change the Technical Specifications ML17037C4131977-07-22022 July 1977 Letter Enclosing Application for Amendment to Operating License and Proposed Changes to Technical Specifications Concerning Changes in Management and Organization ML17037C4141977-07-18018 July 1977 Letter Enclosing an Application for Amendment to Operating License and Proposed Changes to the Technical Specifications to Provide for More Flexible Operation and Concerning Load Line Limit Analysis ML17037C4161977-07-14014 July 1977 Application for Amendment to Operating License and Proposed Change to Technical Specification Concerning the Emergency Cooling System ML17037C4181977-05-19019 May 1977 Letter Enclosing an Application to Amend Operating License and a Requested Change in the Technical Specifications Relating to Instrumentation Used to Monitor Drywell Suppression Chamber Differential Pressure and Suppression .. ML17037C4341977-03-0404 March 1977 Letter Regarding a Preliminary Review of the December 7, 1976 Request for Technical Specification Changes to Reactor Operating Limits After Reload for Cycle 5 Operation and Requesting Additional Information to Complete Review ML17037C4391976-09-30030 September 1976 Letter Requesting Submittal of an Application for License Amendment to Incorporate the Requirements of the Model Technical Specifications ML17037C4531976-01-19019 January 1976 Letter Transmitting an Application for Amendment to Operating License and a Proposed Change to Technical Specifications (Appendix a) to Clarify Cloride and Oxygen Levels ML17037C1771975-12-19019 December 1975 Letter Enclosing a Corrected Attachment to License Amendment No. 11 Change No. 27 to the Technical Specifications Provisional Operating License No. DPR-16 ML17037C1831975-11-0303 November 1975 Letter Regarding Application for Amendment to Technical Specifications and an Inadvertent Error Not Made on the Persons Listed in the Certificate of Service ML17037C4681975-09-23023 September 1975 Letter Regarding a Stress Assisted Corrosion Problem and an Enclosed Safety Evaluation by the Office of NRR - Supporting Amendment to License No. DPR-63 and Changes to the Technical Specifications Inoperable Control Rod .. ML17037C4541975-09-0808 September 1975 Letter Transmitting an Application for Amendment to Operating License and a Proposed Change to Technical Specifications Correcting Errors in a Submittal Made August 15, 1975 in Connection with Reload Cycle 5 2023-05-25
[Table view] Category:Technical Specification
MONTHYEARRS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. ML22292A1312022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Technical Specification Bases, Rev. 69 RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration NMP1L3477, License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise.2022-08-12012 August 2022 License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise. NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-30030 September 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements NMP2L2762, License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2021-05-26026 May 2021 License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability NMP2L2718, Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22019-12-12012 December 2019 Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls NMP2L2693, Technical Specification Bases, Rev. 572018-10-24024 October 2018 Technical Specification Bases, Rev. 57 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 NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note2017-08-22022 August 2017 License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 ML16309A4002016-10-24024 October 2016 Revision 47 to Technical Specification Bases, List of Effective Pages ML16309A4022016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B2.0, Safety Limits (Sls) ML16309A4032016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.0, Limiting Condition for Operation (LCO) Applicability ML16309A4012016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Table of Contents ML16309A4082016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.5, Emergency Core Cooling Systems (ECCS) and Reactor Core Isolation Cooling (RCIC) System ML16309A4132016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.9, Refueling Operations ML16309A4052016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.2, Power Distribution Limits ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. NMP1L3070, License Amendment Request - Reactivity Anomalies Surveillance2016-03-18018 March 2016 License Amendment Request - Reactivity Anomalies Surveillance NMP2L2592, Supplemental Information Regarding TSTF-425 License Amendment Request2015-09-24024 September 2015 Supplemental Information Regarding TSTF-425 License Amendment Request NMP1L3027, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)2015-05-12012 May 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) ML15089A2312015-03-26026 March 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) NMP1L3010, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)2015-03-26026 March 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) NMP2L2576, License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2015-03-23023 March 2015 License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual NMP2L2563, License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change2014-11-17017 November 2014 License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change ML14191A2552014-07-10010 July 2014 Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML12156A3632012-06-0101 June 2012 Emergency License Amendment Request Pursuant to 10 CFR 50.90: Revision of the Main Steam Isolation Valve Allowable Leakage Rate Limit ML11306A2982011-10-27027 October 2011 Submittal of Revision 22 to the Final Safety Analysis Report (Updated), 10 CFR 50.59 Evaluation Summary Report, Technical Specifications Bases Changes, and Report Consistent with 10 CFR 54.37(b) ML11214A2142011-07-25025 July 2011 License Amendment Request, Extension of the Completion Time for Inoperable Diesel Generator - Response to NRC Request for Additional Information ML1109602832011-03-30030 March 2011 License Amendment Request Pursuant to 10 CFR 50.90: Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage ... ML0935000902009-12-0909 December 2009 License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery - Technical Specification 3.8.4, DC Sources - Operating ML0931602572009-10-26026 October 2009 Submittal of Revision 21 to the Final Safety Analysis Report (Updated), 10 CFR 50.59 Evaluation Summary Report, Technical Specifications Bases Changes, and Report Consistent with 10 CFR 54.37(b) ML0907802502009-03-0909 March 2009 Submittal of Amendment Request for Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency ML0906403012009-03-0303 March 2009 License Amendment Request Pursuant to 10 CFR 50.90: Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML0827502992008-09-29029 September 2008 Technical Specifications ML0802501622008-01-24024 January 2008 Response to NRC Request for Additional Information Regarding Nine Mile Point Nuclear Station, Unit No. 1, Revision of Rod Worth Minimizer Limiting Condition for Operation During Startup ML0726401032007-09-19019 September 2007 License Amendment Request for Adoption of TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities. ML0721906052007-07-30030 July 2007 Application for Technical Specification Change TSTF-477, Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process ML0721205922007-07-23023 July 2007 Application for Technical Specification Improvement to Adopt TSTF-476, Revison 1, Improved BPWS Control Rod Insertion Process (NEDO-33091), Using the Consolidated Line Item Improvement ML0721205872007-07-23023 July 2007 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Rod Worth Minimizer Limiting Condition for Operation During Startup - Technical Specification Section 3.1.1.b ML0720504232007-07-12012 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0720504742007-07-12012 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0707800592007-03-15015 March 2007 Technical Specification 4.1.1 Regarding Control Rod System Surveillance Requirements ML0630406022006-10-19019 October 2006 License Amendment Request Pursuant to 10 CFR 50.90: Revision to Control Rod System Surveillance Requirements - Technical Specification 4.1.1 2023-05-25
[Table view] Category:Bases Change
MONTHYEARML22292A1312022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Technical Specification Bases, Rev. 69 RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration NMP1L3477, License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise.2022-08-12012 August 2022 License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise. NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-30030 September 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements NMP2L2762, License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2021-05-26026 May 2021 License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability NMP2L2693, Technical Specification Bases, Rev. 572018-10-24024 October 2018 Technical Specification Bases, Rev. 57 ML16309A4132016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.9, Refueling Operations ML16309A4082016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.5, Emergency Core Cooling Systems (ECCS) and Reactor Core Isolation Cooling (RCIC) System ML16309A4052016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.2, Power Distribution Limits ML16309A4032016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.0, Limiting Condition for Operation (LCO) Applicability ML16309A4022016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B2.0, Safety Limits (Sls) ML16309A4012016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Table of Contents ML16309A4002016-10-24024 October 2016 Revision 47 to Technical Specification Bases, List of Effective Pages ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. NMP1L3070, License Amendment Request - Reactivity Anomalies Surveillance2016-03-18018 March 2016 License Amendment Request - Reactivity Anomalies Surveillance NMP2L2592, Supplemental Information Regarding TSTF-425 License Amendment Request2015-09-24024 September 2015 Supplemental Information Regarding TSTF-425 License Amendment Request ML15089A2312015-03-26026 March 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) NMP1L3010, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)2015-03-26026 March 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) NMP2L2563, License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change2014-11-17017 November 2014 License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change ML12156A3632012-06-0101 June 2012 Emergency License Amendment Request Pursuant to 10 CFR 50.90: Revision of the Main Steam Isolation Valve Allowable Leakage Rate Limit ML11306A2982011-10-27027 October 2011 Submittal of Revision 22 to the Final Safety Analysis Report (Updated), 10 CFR 50.59 Evaluation Summary Report, Technical Specifications Bases Changes, and Report Consistent with 10 CFR 54.37(b) ML11214A2142011-07-25025 July 2011 License Amendment Request, Extension of the Completion Time for Inoperable Diesel Generator - Response to NRC Request for Additional Information ML0931602572009-10-26026 October 2009 Submittal of Revision 21 to the Final Safety Analysis Report (Updated), 10 CFR 50.59 Evaluation Summary Report, Technical Specifications Bases Changes, and Report Consistent with 10 CFR 54.37(b) ML0802501622008-01-24024 January 2008 Response to NRC Request for Additional Information Regarding Nine Mile Point Nuclear Station, Unit No. 1, Revision of Rod Worth Minimizer Limiting Condition for Operation During Startup ML0726401032007-09-19019 September 2007 License Amendment Request for Adoption of TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities. ML0721906052007-07-30030 July 2007 Application for Technical Specification Change TSTF-477, Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process ML0721205872007-07-23023 July 2007 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Rod Worth Minimizer Limiting Condition for Operation During Startup - Technical Specification Section 3.1.1.b ML0721205922007-07-23023 July 2007 Application for Technical Specification Improvement to Adopt TSTF-476, Revison 1, Improved BPWS Control Rod Insertion Process (NEDO-33091), Using the Consolidated Line Item Improvement ML0720504232007-07-12012 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0630406022006-10-19019 October 2006 License Amendment Request Pursuant to 10 CFR 50.90: Revision to Control Rod System Surveillance Requirements - Technical Specification 4.1.1 ML0236505402002-12-19019 December 2002 License Amendment Request Pursuant to 10 CFR 50.90: Update and Clarification of Shutdown Margin Requirements ML17037C4131977-07-22022 July 1977 Letter Enclosing Application for Amendment to Operating License and Proposed Changes to Technical Specifications Concerning Changes in Management and Organization ML17037C4141977-07-18018 July 1977 Letter Enclosing an Application for Amendment to Operating License and Proposed Changes to the Technical Specifications to Provide for More Flexible Operation and Concerning Load Line Limit Analysis ML17037C4181977-05-19019 May 1977 Letter Enclosing an Application to Amend Operating License and a Requested Change in the Technical Specifications Relating to Instrumentation Used to Monitor Drywell Suppression Chamber Differential Pressure and Suppression .. ML17037C1751975-12-24024 December 1975 Letter Regarding Approved Model Technical Specifications Relating to Hydraulic Snubbers and an Enclosed Copy of Revised Model Technical Specifications and Bases ML17037C2721975-01-21021 January 1975 Letter Transmitting Four Proposed Changes to the Technical Specifications Concerning Changes in Plant Organization and Set Points for Reactor Water Levels ML17037C3331972-04-21021 April 1972 Letter Responding to the March 21, 1972 Letter Requesting Additional Information Regarding Proposed Changes to the Technical Specifications and Bases ML17037C3351971-06-18018 June 1971 Letter Responding to the April 14, 1971 Letter Regarding Change No. 4 to the Technical Specifications and Enclosing a New Printing with Changes No. 1 and 3 and a Number of Additional Changes ML18018B0801969-08-22022 August 1969 Appendix a to Provisional Operating License DPR-17 Technical Specifications and Bases 2022-08-12
[Table view] |
Text
NMP2L2563 November 17, 2014 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555
Subject:
Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 NRG Docket No. 50-410 License Amendment Request -Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change 10 CFR 50.90 In accordance with 10 CFR 50.90, Exelon Generation Company, LLC (Exelon) requests an amendment to the Technical Specifications, Appendix A, of Renewed Facility Operating License No. NPF-69 for Nine Mile Point Nuclear Station, Unit 2 (NMP2). The proposed amendment would revise the NMP2 Technical Specification (TS) Allowable Value for the Main Steam Line Tunnel Lead Enclosure Temperature-High instrumentation from an ambient temperature dependent (variable setpoint) to ambient temperature independent (constant Allowable Value). The changes would delete Surveillance Requirement (SR) 3.3.6.1.2 and revise the Allowable Value for Function 1.g on Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation." In addition, the associated Bases will be revised. The implementation of this amendment will enhance plant operational reliability and reduce risk by minimizing the potential for a plant trip function and/or an unnecessary plant shutdown.
In addition, these changes will improve ALARA dose goals and reduce industrial safety risks by minimizing station personnel entries into high-energy steam piping environments.
Therefore, Exelon is requesting an expedited review of this submittal in order to support implementation prior to the next seasonal (summer 2015) temperature adjustments.
Attachment 1 provides the Evaluation of Proposed Technical Specification Changes. Attachment 2 provides the Proposed Technical Specification and Bases Marked-Up Pages.
LAR -Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change November 17, 2014 Page 2 The proposed changes have been reviewed by the NMP Plant Operations Review Committee and approved in accordance with Nuclear Safety Review Board procedures.
Exelon requests approval of the proposed amendment by May 15, 2015. Once approved, the amendment shall be implemented within 60 days. There are no regulatory commitments contained in this request. In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b), Exelon is notifying the State of New York of this application of license amendment by transmitting a copy of this letter and its attachments to the designated State Official.
Should you have any questions concerning this submittal, please contact Ron Reynolds at (610) 765-5247.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 17 1 h day of November 2014. Respectfully, James Barstow Director -Licensing
& Regulatory Affairs Exelon Generation Company, LLC Attachments:
- 1) Evaluation of Proposed Technical Specification Changes 2) Proposed Technical Specification and Bases Marked-Up Pages cc: USNRC Regional Administrator, Region I USNRC Project Manager, NMP USNRC Senior Resident Inspector, NMP A. L. Peterson, NYSERDA w/attachments w/attachments w/attachments w/attachments ATTACHMENT 1 EVALUATION OF PROPOSED TECHNICAL SPECIFICATION CHANGES
SUBJECT:
Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change 1.0
SUMMARY
DESCRIPTION
2.0 DETAILED
DESCRIPTION
3.0 TECHNICAL
EVALUATION
4.0 REGULA
TORY EVALUATION
4.1 Applicable
Regulatory Requirements/Criteria
4.2 Precedent
4.3 No Significant Hazards Consideration
4.4 Conclusions
5.0 ENVIRONMENTAL
CONSIDERATION
6.0 REFERENCES
Evaluation of Proposed Technical Specification Changes Attachment 1 Page 1of7 Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change 1.0
SUMMARY
DESCRIPTION This evaluation supports a request to amend Renewed Operating License No. NPF-69 for Nine Mile Point Nuclear Station, Unit 2 (NMP2). The proposed changes would revise the Technical Specification (TS) instrument Allowable Value (AV) associated with the Leak Detection System (LOS) for the Main Steam Line Tunnel Lead Enclosure and delete the associated Surveillance Requirement (SR). This License Amendment Request would change the Main Steam Line Tunnel Lead Enclosure leak detection temperature setpoint from ambient lead enclosure area temperature dependent (i.e., variable AV) to ambient temperature independent (i.e., constant AV). The constant AV would use the upper limit of the variable temperature range currently approved and identified in the TS. This constant setpoint temperature would eliminate future temperature adjustments for winter and summer months in the Main Steam Line Tunnel Lead Enclosure.
In addition, the proposed changes would enhance plant operational reliability and reduce risk by minimizing the potential for a plant trip function and/or unnecessary plant shutdown.
These proposed changes will improve ALARA dose goals and reduce industrial safety risks by minimizing station personnel entries into high-energy steam piping environments.
Exelon Generation Company, LLC (Exelon) requests approval of the proposed changes. Once approved, the amendment shall be implemented within 60 days. 2.0 DETAILED DESCRIPTION The proposed changes would revise the AV temperature for the Main Steam Line Tunnel Lead Enclosure Temperature
-High isolation AV (TS Table 3.3.6.1-1, Function No. 1.g) from ambient temperature dependent
+ (0.6)( Tamb-90°F) provided the absence of steam leaks in the Main Steam Line Tunnel Lead Enclosure area is verified by visual inspection prior to establishing the Allowable Value) to a constant value based on the worst case winter operating conditions.
The associated leak rate would change from 25 gallon per minute (gpm) to 45 gpm equivalent condensate steam leak as the design basis for the Main Steam Line Tunnel Lead Enclosure.
The proposed changes would also delete the SR 3.3.6.1.2 as the seasonal adjustment to the setpoint temperature for the Main Steam Line Tunnel Lead Enclosure would no longer be necessary.
Footnote (b) would also be deleted from TS Table 3.3.6.1-1.
With a constant AV, the need to perform LOS temperature adjustments for the summer and again for the winter months would be eliminated.
The plant would reduce the potential for a plant trip function and/or unnecessary plant shutdown in order to recalibrate the temperature trip units in the Main Steam Line Tunnel Lead Enclosure associated with the LOS temperature adjustments.
The purpose of the leak detection system instrumentation and controls is to detect and provide the signals necessary to isolate leakage from the reactor coolant pressure boundary before predetermined limits are exceeded.
Evaluation of Proposed Technical Specification Changes Attachment 1 Page 2 of 7 The Main Steam Line Tunnel Lead Enclosure is constantly monitored for leaks by the LOS using dual-element thermocouples for sensing high ambient temperature in the area. If a leak is detected, the detection system responds by triggering an annunciator and initiating a steam line isolation trip logic signal. This license amendment request only affects the instrument isolation setpoints of the circuits that monitor the ambient temperature and provide system isolations on high ambient temperature for the Main Steam Line Tunnel Lead Enclosure.
The LOS is comprised of Temperature Indicating Switches (TIS) that receive data from temperature elements located in the area being monitored and determine if the temperature has reached its isolation setpoints.
If reached, an automatic isolation I alarm signal is initiated and an annunciator is activated in the control room. The TIS setpoints are selected high enough to avoid spurious isolations, yet low enough to provide timely detection of a small leak and isolation at 45 gpm for the Main Steam Line Tunnel Lead Enclosure.
3.0 TECHNICAL
EVALUATION Background The function of the Main Steam Line Tunnel Lead Enclosure high temperature detection circuitry is to detect a steam leak in the lead enclosure area. The Main Steam Line Tunnel Lead Enclosure has 12 temperature sensors (2MSS*TE69A/B/C/O, 2MSS*TE70A/B/C/O, and 2MSS*TE71 A/B/C/O).
These sensors monitor area temperatures at three locations in the lead enclosure, and each location has four sensors. Each sensor has a temperature switch (2MSS*TS1069A/B/C/O, 2MSS*TS1070A/B/C/O, and 2MSS*TS1071A/B/C/O) which actuates when its temperature setpoint is exceeded and closes the Main Steam Isolation Valves (MSIVs). The MSIVs closure logic is arranged in a "one-out-of-two taken twice" for each location.
In order to maintain sufficient operating margin during the summer season, the setpoints for the Main Steam Line Tunnel Lead Enclosure temperature switches (2MSS*TS1069A/B/C/O, 2MSS*TS1070A/B/C/O, and 2MSS*TS1071A/B/C/O) are seasonally adjusted.
This process has the potential to lead to half isolation and possibly a plant shutdown.
In addition, it requires increased temperature surveillance to guard against Main Steam Line Tunnel Lead Enclosure temperature reduction.
The existing Analytical Limit (AL) for the lead enclosure LOS varies with the lead enclosure temperatures, from 156 to 180°F. The supporting analysis assumed a 25 gpm (8.35 lbm = 1 gallon) steam leak in the lead enclosure and determined the AL as a function of the initial lead enclosure temperature (90 to 130°F). This approach provided greater operational flexibility.
However, it requires seasonal setpoint adjustments and has the potential for inadvertent MSIV closure and subsequent plant shutdown.
The temperature response calculations were performed using the Stone & Webster Engineering Corporation (SWEC) computer code, THREEO Subcompartment Transient Response Code. Proposed Technical Specification Changes This License Amendment Request would change the Main Steam Line Tunnel Lead Enclosure leak detection temperature setpoint from lead enclosure ambient temperature dependent (AV varies from 151.6 to 175.6°F) to ambient temperature independent (i.e., constant AV). The Evaluation of Proposed Technical Specification Changes Attachment 1 Page 3 of 7 temperature setpoint would be changed to the maximum currently allowed by the Technical Specifications (Table 3.3.6.1-1, Function 1.g; Allowable Value= s175.6°F).
To achieve this change, the leak detection basis requires revision from 25 to 45 gpm (equivalent steam leakage) for the lead enclosure only. Other locations in the main steam tunnel remain capable of detection of a 25 gpm equivalent steam leak. In addition, the TS SR 3.3.6.1.2, "Verify the actual ambient temperature reading for all OPERABLE channels is T amb," is deleted. The specific changes to Technical Specifications and associated Bases are shown on Attachment
- 2. Evaluation Setpoint Change: To support the use of the existing maximum AV of 175.6°F for the Main Steam Line Tunnel Lead Enclosure temperature, the existing design basis model and assumptions are used in the revised analysis.
The lead enclosure temperature response is calculated using GOTHIC computer code (version 8.0). The existing design basis model used the SWEC THREED computer code. The GOTHIC model is benchmarked against the TH REED code by reproducing the temperature transients for a 25 gpm equivalent steam leak. It is concluded that the GOTHIC model and methods as implemented result in essentially the same temperatures (i.e., within 2°F) as the THREED model used by SWEC for the original temperature response calculations.
Using this GOTHIC model, the steam leakage that results in AL of 180°F corresponding to 175.6°F AV is defined. Using the most limiting winter conditions (same as those assumed in the existing analysis), the leak rate corresponding to 180°F AL is a 45 gpm steam leak. Table 1 lists the parameters before and after the proposed amendment.
The setpoint methodology remains the same as the current setpoint methodology.
As seen in Table 1, the proposed setpoints (AL, AV, and TSP) are the same as those currently allowed by the existing setpoint calculation and the current Technical Specification.
Table 1 Current Value vs. Proposed Change for Specific Parameters Parameter Before Proposed Change After Proposed Change Analytical Limit 156 -180°F 180°F Allowable Value 151.6-175.6°F 175.6°F Trip Set Point (Upper) 148.2 172.2°F 172.2°F Leak Rate 25aom 45qpm The proposed change is not expected to reduce operating temperature margin during the summer season because the above values have been proved satisfactory.
Critical Crack Size: The critical crack size leak rate is described in USAA Section 5.2.5.5.3.
Each Main Steam Line in the lead enclosure is 28 inch OD carbon steel pipe (A 106 Gr C) with 1.339 inch nominal wall thickness.
Using the same approach described in USAA Section 5.2.5.5.3, the longitudinal Evaluation of Proposed Technical Specification Changes Attachment 1 Page 4 of 7 critical crack is approximately 37 inches. The corresponding leak rate is estimated to be greater than 450 gpm, or 10 times the leak rate used for the leak detection setpoint.
Based on the above, it is concluded that the LDS will isolate the MSL with adequate margin for contingencies, regarding a crack size large enough to propagate rapidly. Radiological Impact: The increase in the steam leak rate has no impact on the radiological consequences associated with the Main Steam Line Break (MSLB} described in USAR Section 15.6.4, Steam System Piping Break Outside Containment.
The radiological consequences (using the same source terms and dispersion factors used for the MSLB} associated with the 45 gpm steam leak for one hour is bounded by the MSLB described in USAR Section 15.6.4. Eguipment Qualification and Structural Impact The peak temperatures associated with a 25 or 45 gpm equivalent steam leak are essentially the same, 180°F. The maximum temperature in the lead enclosure is established by the MSLB. Therefore, there is no adverse impact on the SSCs located in the steam tunnel. Impact of TS SR 3.3.6.1.2 Deletion:
The new AV, 175.6°F, is based on the worst case winter condition.
The initial lead enclosure ambient temperature assumed in the analysis is 80°F, well below the typical winter or summer time operating temperature in the lead enclosure.
Typical winter time operating temperature in the lead enclosure ranges from 100 to 115°F. The lowest recorded temperature between 2009 and 2014 is 95°F for a period of approximately two days. Thus, the new AV is based on sufficiently low ambient temperature.
Therefore, periodic surveillance is not required consistent with the existing TS SR 3.3.6.1.2 Bases.
4.0 REGULATORY EVALUATION
4.1 Applicable
Regulatory Requirements/Criteria The proposed changes have been evaluated to determine whether applicable regulations and requirements continue to be met. Exelon Generation Company, LLC (Exelon) has determined that the proposed changes do not require any exemptions or relief from regulatory requirements other than the TSs. The following applicable regulations and regulatory requirements were reviewed in making this determination:
10 CFR 50 Appendix A, General Design Criterion (GDC) 13, "Instrumentation and control," requires, in part, that instrumentation be provided to monitor variables and systems, and that controls are provided to maintain these variables and systems within prescribed operating ranges. 10 CFR 50 Appendix A, GDC 20, "Protection system functions," requires, in part, that the protection system be designed to initiate automatically the operation of appropriate systems, including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences.
Evaluation of Proposed Technical Specification Changes Attachment 1 Page 5of7 10 CFR 50 Appendix A, GDC 30, "Quality of reactor coolant pressure boundary," requires, in part, that means shall be provided for detecting and, to the extent practical, identifying the location of the source of reactor coolant leakage. Regulatory Guide 1.105, Revision "Instrument Setpoints for Safety-Related Systems," describes a method acceptable to the NRC staff for complying with the NRC's regulations for ensuring that setpoints for safety-related instrumentation are initially within and remain within the TS limits. The NMP2 design complies with the Regulatory Position (Paragraph C) of this guide. NMP2 USAA Table 1.8-1 states: "The Unit 2 project complies with the Regulatory Position (Paragraph C) of this guide." NMP2 USAA Section 7.1.2.3 states, in part: "The trip setpoint (instrument setpoint) and allowable value (Technical Specification limit) are contained in Technical Specifications.
These parameters are all appropriately separated from each other and their selection is based on instrument accuracy, calibration capability, and design drift (estimated) allowance data. The setpoints are within the instrument accuracy range. The established setpoints provide margin to satisfy both safety requirements and plant availability objectives." 4.2 Precedent A 1992 Susquehanna License Amendment (Reference
- 1) was approved for the Leak Detection Function in the Turbine Building Main Steam Tunnel that changed the leakage basis from a 25 gpm leak to a 65 gpm equivalent leak during winter operations.
This amendment revised the isolation setpoint from 117°F to 197°F. A 1996 LaSalle License Amendment (Reference
- 2) was approved for changes to setpoints for the automatic primary containment isolation on the Main Steam Line Tunnel which changed the leakage basis from 25 gpm to 100 gpm. The amendment revised the Main Steam Tunnel Differential-High isolation signal from s36°F to S65°F. A 2004 Perry License Amendment (Reference
- 3) was approved for changes to the Primary Containment and Drywell Isolation Instrumentation to increase the analytical limit for detected temperature resulting in a change to the AV related to the setpoint for the Main steam Line Turbine Building temperature-High system isolation function from 138.9 °F to 149.6°F. This temperature increase corresponds to an increase in the LOS upper boundary leakage limit from an equivalent steam leakage value of 25 gpm to 280 gpm. 4.3 No Significant Hazards Consideration Exelon has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response:
No.
Evaluation of Proposed Technical Specification Changes Attachment 1 Page 6 of 7 The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated because the performance of any equipment credited in the radiological consequences of an accident is not affected by the change in the leak detection capability.
The Main Steam Line Tunnel Lead Enclosure Temperature
-High is provided to detect a steam leak in the lead enclosure and provides diversity to the high flow instrumentation.
This function provides a mitigating action for a steam leak in the Main Steam Line Tunnel Lead Enclosure, which could lead to a pipe break. This function does not affect any accident precursors, and the proposed changes do not affect the leak detection capability.
Additionally, the proposed changes do not degrade the performance of or increase the challenges to any safety systems assumed to function in the accident analysis.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response:
No. The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed changes do not add or remove equipment and do not physically alter the isolation instrumentation.
In addition, the Main Steam Line Tunnel Lead Enclosure LOS is not utilized in a different manner. The proposed changes do not introduce any new accident initiators and new failure modes, nor do they reduce or adversely affect the capabilities of any plant structure, system, or component to perform their safety function.
The Main Steam Line Tunnel Lead Enclosure LOS will continue to be operated in the same manner. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response:
No. The proposed changes do not involve a significant reduction in a margin of safety because the changes eliminate the temperature setpoint dependency on lead enclosure temperature while maintaining the existing upper AV = 175.6°F, that was previously evaluated and approved.
There is no adverse impact on the existing equipment capability as well as associated structures.
The increase in the steam leak rate and associated crack size continues to be well below the leak rate associated with critical crack size that leads to pipe break. The proposed changes continue to provide the same level of protection against a main steam line break as the existing setpoint values. Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
Evaluation of Proposed Technical Specification Changes Attachment 1 Page 7of7 Based on the above, Exelon concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c) and, accordingly, a finding of no significant hazards consideration is justified.
4.4 Conclusions
In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. 5.0 ENVIRONMENTAL CONSIDERATION A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 1 O CFR 20, or would change an inspection or surveillance requirement.
However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 REFERENCES
- 1. Isolation Setpoint for the Leak Detection Temperature Function in the Turbine Building Main Steam Tunnel, Susquehanna Steam Electric Station, Units 1 and 2 (TAC NOS. M80222 and M80223), dated May 21, 1992 2. Issuance of Amendments (TAC NOS. M94583 and M94779), dated April 4, 1996 (ML021130125) (LaSalle County, Units 1 and 2) 3. Perry Nuclear Power Plant, Unit 1 -Issuance of Amendment (TAC NO. MC0342), dated July 9, 2004 (ML041810686)
ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION and BASES MARKED-UP PAGES (Unit 2) TS Pages 3.3.6.1-4 and -6 Bases Pages B3.3.6.1-12 and -35 Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS
- 1. Refer ta Table 3.3.6.1-1 ta determine which SRs apply far each Primary Containment Isolation Function.
- 2. When a channel is placed in an inoperable status solely far performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed far up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains isolation capability.
SURVEILLANCE FREQUENCY SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.6 NMP2 Perform CHANNEL CHECK. Only required to be met *11hon tho /\,llowable Value is adjusted in aocordanoe with Table 3.3.6.1 1, footnote (b). Perform CHANNEL FUNCTIONAL TEST. Calibrate the trip unit. Perform CHANNEL CALIBRATION.
Perform LOGIC SYSTEM FUNCTIONAL TEST. 3.3.6.1-4 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 12 ROUFS 92 days 92 days 24 months 24 months (continued)
Amendment 91 Primary Containment Isolation Instrumentation 3.3.6.1 Table3.3.6.1*1(page1 of5) Primary Containment Isolation Instrumentation MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE
- 1. Main Steam Line Isolation
- a. Reactor Vessel Water 1,2,3 2 D SR 3.3.6.1.1 10.8 Inches Level Low Low Low, SR 3.3.6.1.3 Level 1 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7
- b. Main Steam Line Pressure 2 E SR 3.3.6.1.1 746 psig Low SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7
- c. Main Steam Line 1,2,3 2 per MSL D SR 3.3.6.1.1
,:; 184.4 psid Flow High SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7
- d. Condenser Vacuum -Low 1,2(a), 2 D SR 3.3.6.1.1
7.6 Inches
SR 3.3.6.1.3 Hg vacuum 3(a) SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.6
- e. Main Steam Line 1,2,3 2 D SR 3.3.6.1.1
,:; 170.6°F Tunnel SR 3.3.6.1.3 Temperature
-High SR 3.3.6.1.5 SR 3.3.6.1.6
- f. Main Steam Line 1,2,3 2 D SR 3.3.6.1.1 71.7°F Tunnel Differential SR 3.3.6.1.3 Temperature
-High SR 3.3.6.1.5 SR 3.3.6.1.6
- g. Main Steam Line 1,2,3 2 per area D SR 3.3.6.1.1 Tunnel Lead Enclosure SR 3.3.6A.2 Temperature
-High SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6
- h. Manual Initiation 1,2,3 4 G SR 3.3.6.1.6 NA (a) With any turbine stop valve not closed. fb1 451.6°F + \0.e)(Tamo 90°F) and<< 175.6°F pF<wided the absenoe of steam leaks in the main oleam line tunnel lead by 'lisual lnspeetien prier te
\lalue. NMP2 3.3.6.1-6 Amendment 94, 140 BASES APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY NMP2 Primary Containment Isolation Instrumentation B 3.3.6.1 1.g. Main Steam Line Tunnel Lead Enclosure Temperature
-High (continued) occurs when a very small leak has occurred in any one of the three areas of the enclosure.
If the small leak is allowed to continue without isolation, offsite dose limits may be reached. However, credit for these instruments is not taken in any transient or accident analysis in the USAR, since bounding analyses are performed for large breaks such as MSL breaks. Main Steam Line Tunnel Lead Enclosure Temperature
-High signals are initiated from thermocouples located in the area being monitored.
Twelve channels of Main Steam Line Tunnel Lead Enclosure Temperature
-High Function are available and are required to be OPERABLE (four in each of the three areas) to ensure that no single instrument failure can preclude the isolation function.
The Main Steam Line Tunnel Lead Enclosure Temperature
-High Allowable Value is chosen to detect a leak equivalent to gpm. In addition, as ambient temperature in the main steam line tunnel lead enclosure inereases, the Allowable Value is allowed to be inoreased as described in footnote (b) to Table 3.3.6.1 1. This is permitted pre*1ided the main steam line tunnel lead enclosure is visually inspected to ensure the ambient temperature increase is not due to a steam leak. This Function isolates the Group 1 valves. 1.h. Manual Initiation The Manual Initiation switch and push button channels introduce signals into the MSL isolation logic that are redundant to the automatic protective instrumentation and provide manual isolation capability.
There is no specific USAR safety analysis that takes credit for this Function.
It is retained for overall redundancy and diversity of the isolation function as required by the NRC in the plant licensing basis. There are four switch and push buttons (with two channels per switch and push button) for the logic, with two switch and push buttons per trip system. Eight channels of Manual (continued)
B 3.3.6.1-12 Revision O BASES SURVEILLANCE REQUIREMENTS (continued)
NMP2 Primary Containment Isolation Instrumentation B 3.3.6.1 SR This SuA<eillanoe
erifies that, when the Allowable
\lalue for Ina Main Steam bine +unnel bead Enclosure Tumperature Migl=! Funotien is adjusted based on the formula in footnate (b) te Tuble 3.3.6.1 1, the aotual ambient temperature, as measured by the Main Stearn line Tunnel bead enolesure
+emperatt:tre High Funotion channels, is greateF thaR or eetual te the ambient tempeFature (1'am11) used te adjust the Allw.vable
\lalue. Only the OPERABLE Main Steam line l'unnel bead Enolosure
+ernperature High Funotion ohannels are reetuired te be 'Jerified.
As stated in the Note te tne 8R, the 8R is only reetuired to be met 'Nhen the Allowable Value is adjusted in aooordanoe
'Nith Tuble 3.3.6.1 1, footnote (b), since the normal Allo'l.<able Value is based on a su#ioieAtiy loi.*.i ambient temperature that the ¥erifioation is net neoessary.
The Freetuenoy of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is based on the need te periodioally monitor the ambient temperature to eAsure the Allov.'able Vah:1e remains valid, and \*.*as ohoseA to seineide with the GMANNEL GMEGK Freetuensy. ,A,s requireEI by SR 3.0A, the SR must alse be performeEI prior to adjusting the AllO\\table Value, sinoe the SuNeillanoe must be met at all times when the Allo*1.<able Value has beeA aEljusted (thus te rneet the SR when the Allo*.-..able value has been adjusted, it must aetually be performeEI prior to the adjustment).
SR 3.3.6.1.3 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the channel will perform the intended function.
Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.
The Frequency of 92 days is based on reliability analyses described in References 11 and 12. SR 3.3.6.1.4 The calibration of trip units consists of a test to provide a check of the actual trip setpoints.
The channel must be declared inoperable if the trip setting is discovered to be less conservative than the Allowable Value specified in B 3.3.6.1-35 (continued)
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