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Category:Letter type:NLS
MONTHYEARNLS2024053, Licensee Guarantees of Payment of Deferred Premiums2024-07-30030 July 2024 Licensee Guarantees of Payment of Deferred Premiums NLS2024055, Data from Metamic Coupon Sampling Program2024-07-29029 July 2024 Data from Metamic Coupon Sampling Program NLS2024052, Supplement to the Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow2024-07-24024 July 2024 Supplement to the Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow NLS2024051, Supplement to the Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program2024-07-0303 July 2024 Supplement to the Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program NLS2024025, License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation2024-05-0909 May 2024 License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation NLS2024037, 2023 Annual Radiological Environmental Report2024-05-0808 May 2024 2023 Annual Radiological Environmental Report NLS2024030, Annual Radioactive Effluent Release Report2024-04-25025 April 2024 Annual Radioactive Effluent Release Report NLS2024033, Preparation and Scheduling of Operator Licensing Examinations2024-04-25025 April 2024 Preparation and Scheduling of Operator Licensing Examinations NLS2024031, Notice of Intent to Apply for Subsequent Renewal of Operating License2024-04-22022 April 2024 Notice of Intent to Apply for Subsequent Renewal of Operating License NLS2024036, Nebraska Public Power District 2023 Financial Report2024-04-19019 April 2024 Nebraska Public Power District 2023 Financial Report NLS2024027, Response to NRC Request for Additional Information Regarding Application for the Emergency License Amendment Request to Revise Technical Specifications 3 .3 .1.1, Reactor Protection (RPS) Instrumentation2024-04-0303 April 2024 Response to NRC Request for Additional Information Regarding Application for the Emergency License Amendment Request to Revise Technical Specifications 3 .3 .1.1, Reactor Protection (RPS) Instrumentation NLS2024024, Emergency License Amendment Request to Revise Technical Specifications 3.3.1.1, Reactor Protection (RPS) Instrumentation2024-04-0101 April 2024 Emergency License Amendment Request to Revise Technical Specifications 3.3.1.1, Reactor Protection (RPS) Instrumentation NLS2024018, Property Insurance Coverage2024-03-20020 March 2024 Property Insurance Coverage NLS2024017, Response to an Apparent Violation in NRC Inspection Report 05000298/2023012; EA-24-0012024-03-0808 March 2024 Response to an Apparent Violation in NRC Inspection Report 05000298/2023012; EA-24-001 NLS2024009, Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Support Inspection of2024-03-0808 March 2024 Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Support Inspection of NLS2024001, Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow2024-02-16016 February 2024 Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow NLS2024006, Response to Nuclear Regulatory Commissions Request for Additional Information for Relief Request RC3-022024-01-25025 January 2024 Response to Nuclear Regulatory Commissions Request for Additional Information for Relief Request RC3-02 NLS2024006, Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-022024-01-25025 January 2024 Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-02 NLS2024007, Emergency Plan Implementing Procedure 5.7.1, Revision 732024-01-16016 January 2024 Emergency Plan Implementing Procedure 5.7.1, Revision 73 NLS2024003, 30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector2024-01-15015 January 2024 30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector NLS2024004, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20232024-01-10010 January 2024 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2023 NLS2023053, ISFSI, Supplement to Exemption Request from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-30030 November 2023 ISFSI, Supplement to Exemption Request from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NLS2023050, 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 NLS2023045, Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program2023-11-15015 November 2023 Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program NLS2023051, Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-10-10010 October 2023 Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2023049, 10 CFR Part 21 Report Regarding HGA Relays2023-09-0606 September 2023 10 CFR Part 21 Report Regarding HGA Relays NLS2023029, License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks2023-09-0606 September 2023 License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks NLS2023047, Licensee Guarantees of Payment of Deferred Premiums2023-07-26026 July 2023 Licensee Guarantees of Payment of Deferred Premiums NLS2023033, 10 CFR 50.55a Relief Request RC3-022023-06-27027 June 2023 10 CFR 50.55a Relief Request RC3-02 NLS2023039, Preparation and Scheduling of Operator Licensing Examinations2023-06-0101 June 2023 Preparation and Scheduling of Operator Licensing Examinations NLS2023038, Nebraska Public Power District 2022 Financial Report2023-05-22022 May 2023 Nebraska Public Power District 2022 Financial Report NLS2023031, Annual Radiological Environmental Report2023-05-11011 May 2023 Annual Radiological Environmental Report NLS2023017, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2023018, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NLS2023030, Annual Radioactive Effluent Release Report2023-04-27027 April 2023 Annual Radioactive Effluent Release Report NLS2023007, Technical Specification Bases Changes2023-04-17017 April 2023 Technical Specification Bases Changes NLS2023027, Annual Report of Individual Exposure Monitoring2023-04-13013 April 2023 Annual Report of Individual Exposure Monitoring NLS2023021, Quality Assurance Program Changes2023-04-10010 April 2023 Quality Assurance Program Changes NLS2023020, Decommissioning Funding2023-03-29029 March 2023 Decommissioning Funding NLS2023019, Property Insurance Coverage2023-03-23023 March 2023 Property Insurance Coverage NLS2023010, Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station2023-02-0909 February 2023 Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station NLS2023005, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20222023-01-19019 January 2023 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2022 NLS2022054, Preparation and Scheduling of Operator Licensing Examinations2023-01-0505 January 2023 Preparation and Scheduling of Operator Licensing Examinations NLS2022055, Emergency Plan, Revision 812023-01-0404 January 2023 Emergency Plan, Revision 81 NLS2022053, CNS-2022-11 Post Exam Submittal2022-11-22022 November 2022 CNS-2022-11 Post Exam Submittal NLS2022050, Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library2022-11-0909 November 2022 Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library NLS2022048, Management Change and Correspondence Update2022-11-0101 November 2022 Management Change and Correspondence Update NLS2022047, Core Operating Limits Report, Cycle 33, Revision 02022-10-14014 October 2022 Core Operating Limits Report, Cycle 33, Revision 0 NLS2022042, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2022-10-0707 October 2022 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report NLS2022037, Emergency Plan, Revision 80, Summary of 50.54(q) Analyses2022-08-18018 August 2022 Emergency Plan, Revision 80, Summary of 50.54(q) Analyses 2024-07-30
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML24134A1782024-07-0303 July 2024 Issuance of Amendment No. 276 Revision to Technical Specification 3.8.3, Diesel Fuel Oil, Lube Oil and Starting Air, to Allow for Cleaning, Inspection and Any Needed Repairs During Refuel Outage 33 NLS2024025, License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation2024-05-0909 May 2024 License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation NLS2024024, Emergency License Amendment Request to Revise Technical Specifications 3.3.1.1, Reactor Protection (RPS) Instrumentation2024-04-0101 April 2024 Emergency License Amendment Request to Revise Technical Specifications 3.3.1.1, Reactor Protection (RPS) Instrumentation NLS2024001, Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow2024-02-16016 February 2024 Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow NLS2023045, Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program2023-11-15015 November 2023 Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program NLS2023029, License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks2023-09-0606 September 2023 License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks NLS2023017, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2023007, Technical Specification Bases Changes2023-04-17017 April 2023 Technical Specification Bases Changes ML21350A0582021-12-21021 December 2021 Withdrawal of an Amendment Request ML21340A2362021-12-20020 December 2021 Issuance of Amendment No. 270 Adoption of Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements NLS2021056, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2021-11-16016 November 2021 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2021018, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-05-11011 May 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements NLS2021015, (CNS) - Technical Specification Bases Changes2021-04-16016 April 2021 (CNS) - Technical Specification Bases Changes NLS2020004, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2020-04-0101 April 2020 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules NLS2020007, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process2020-04-0101 April 2020 Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process NLS2019022, Application for Technical Specifications Improvement to Eliminate Requirements for Hydrogen/Oxygen Monitors (TSTF-447, Rev. 1)2019-05-23023 May 2019 Application for Technical Specifications Improvement to Eliminate Requirements for Hydrogen/Oxygen Monitors (TSTF-447, Rev. 1) NLS2019020, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit Mcpr.2019-05-23023 May 2019 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit Mcpr. NLS2019011, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.2019-02-28028 February 2019 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation. NLS2018010, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.2018-06-11011 June 2018 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control. ML18137A2102018-05-10010 May 2018 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio NLS2016046, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify Surveillance Requirement Usage Rule Application to Section 5.5 Testing.2016-08-26026 August 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify Surveillance Requirement Usage Rule Application to Section 5.5 Testing. NLS2016038, Supplement to License Amendment Request to Replace Figure with Text in Technical Specifications2016-06-13013 June 2016 Supplement to License Amendment Request to Replace Figure with Text in Technical Specifications ML16120A3702016-04-21021 April 2016 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio NLS2016010, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2016-03-22022 March 2016 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program NLS2016002, Application to Revise Technical Specifications to Adopt TSTF 535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs.2016-03-11011 March 2016 Application to Revise Technical Specifications to Adopt TSTF 535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs. NLS2015103, License Amendment Request to Replace Figure with Text in Technical Specifications2015-09-0808 September 2015 License Amendment Request to Replace Figure with Text in Technical Specifications NLS2014087, License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function2015-01-15015 January 2015 License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function NLS2014030, License Amendment Request to Delete Condensate Storage Tank as an Alternate Source of Makeup Water2014-08-26026 August 2014 License Amendment Request to Delete Condensate Storage Tank as an Alternate Source of Makeup Water NLS2014028, License Amendment Request to Move Linear Heat Generation Rate (LHGR) and Single Loop Operation LHGR Limit from Technical Requirements Manual to Technical Specifications2014-07-17017 July 2014 License Amendment Request to Move Linear Heat Generation Rate (LHGR) and Single Loop Operation LHGR Limit from Technical Requirements Manual to Technical Specifications NLS2014035, License Amendment Request to Eliminate Requirements for Post Accident Sampling System for Boiling Water Reactors Using the Consolidated Line Item Improvement Process2014-07-14014 July 2014 License Amendment Request to Eliminate Requirements for Post Accident Sampling System for Boiling Water Reactors Using the Consolidated Line Item Improvement Process NLS2014022, License Amendment Request - Revision of Cyber Security Plan Implementation Schedule2014-03-14014 March 2014 License Amendment Request - Revision of Cyber Security Plan Implementation Schedule NLS2013014, License Amendment Request to Revise License Renewal License Condition 2.E2013-02-12012 February 2013 License Amendment Request to Revise License Renewal License Condition 2.E NLS2012042, Nebraska Public Power District (NPPD) - License Amendment Request for DPR- 46 for Cooper Nuclear Station to Revise the Physical Protection Protection License Condition Related to the Cyber Security Plan2012-06-14014 June 2012 Nebraska Public Power District (NPPD) - License Amendment Request for DPR- 46 for Cooper Nuclear Station to Revise the Physical Protection Protection License Condition Related to the Cyber Security Plan ML12157A2062012-05-30030 May 2012 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio NLS2012006, Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c)2012-04-24024 April 2012 Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c) NLS2011071, License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a2011-09-16016 September 2011 License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a NLS2011026, License Amendment Request for Administrative Revisions to Technical Specifications and to Remove an Expired One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve2011-03-26026 March 2011 License Amendment Request for Administrative Revisions to Technical Specifications and to Remove an Expired One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve ML1101002912011-01-0505 January 2011 Cooper - License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves NLS2010043, License Amendment Request on Non-Conservative Battery Terminal Voltage and Specific Gravity in Technical Specification Surveillance Requirements2010-10-29029 October 2010 License Amendment Request on Non-Conservative Battery Terminal Voltage and Specific Gravity in Technical Specification Surveillance Requirements NLS2010006, License Amendment Request to Correct Power Factor Limit and to Incorporate a Generic Revision in Technical Specification Surveillance Requirement 3.8.1.92010-02-25025 February 2010 License Amendment Request to Correct Power Factor Limit and to Incorporate a Generic Revision in Technical Specification Surveillance Requirement 3.8.1.9 ML1001900422010-02-0303 February 2010 Summary of Telephone Conference Call Held on 1/8/2010, Between the U.S. NRC and Nebraska Public Power District Related to a Clarification for Certain Responses to Requests for Additional Information for Cooper Nuclear Station ML0934309332009-12-0707 December 2009 SAMA Meteorological Anomaly Related to the Cooper Nuclear Station License Renewal Application Cooper Nuclear Station, Docket No. 50-298, DPR-46 NLS2009084, License Amendment Request for Approval of the Cyber Security Plan2009-11-19019 November 2009 License Amendment Request for Approval of the Cyber Security Plan NLS2009034, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2009-06-0202 June 2009 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process NLS2009010, License Amendment Request to Revise Nonconservative Battery Resistance Technical Specification Surveillance Requirements2009-03-11011 March 2009 License Amendment Request to Revise Nonconservative Battery Resistance Technical Specification Surveillance Requirements ML0829107682008-10-13013 October 2008 Cooper Nuclear Station - License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences ML0830302502008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Environmental Report, Figure 2.1-1 - Figure 2.3.3 ML0830302462008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Appendix E, Environmental Report ML0830302512008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Environmental Report, Figure 2.4-1 - Figure 2.12-2 ML0830302442008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Appendix D, Technical Specification Changes 2024-07-03
[Table view] Category:Technical Specification
MONTHYEARNLS2024051, Supplement to the Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program2024-07-0303 July 2024 Supplement to the Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program NLS2024025, License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation2024-05-0909 May 2024 License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation NLS2023029, License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks2023-09-0606 September 2023 License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks NLS2023018, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NLS2023007, Technical Specification Bases Changes2023-04-17017 April 2023 Technical Specification Bases Changes NLS2022005, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-06-16016 June 2022 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements NLS2021056, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2021-11-16016 November 2021 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2021015, (CNS) - Technical Specification Bases Changes2021-04-16016 April 2021 (CNS) - Technical Specification Bases Changes NLS2020004, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2020-04-0101 April 2020 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules NLS2020007, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process2020-04-0101 April 2020 Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process NLS2019020, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit Mcpr.2019-05-23023 May 2019 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit Mcpr. NLS2019022, Application for Technical Specifications Improvement to Eliminate Requirements for Hydrogen/Oxygen Monitors (TSTF-447, Rev. 1)2019-05-23023 May 2019 Application for Technical Specifications Improvement to Eliminate Requirements for Hydrogen/Oxygen Monitors (TSTF-447, Rev. 1) NLS2017048, Submittal of Application to Revise Technical Specifications to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control2017-08-0707 August 2017 Submittal of Application to Revise Technical Specifications to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control NLS2017033, Technical Specification Bases Changes2017-04-0707 April 2017 Technical Specification Bases Changes NLS2016002, Application to Revise Technical Specifications to Adopt TSTF 535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs.2016-03-11011 March 2016 Application to Revise Technical Specifications to Adopt TSTF 535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs. NLS2015040, Technical Specification Bases Changes2015-04-15015 April 2015 Technical Specification Bases Changes NLS2014028, License Amendment Request to Move Linear Heat Generation Rate (LHGR) and Single Loop Operation LHGR Limit from Technical Requirements Manual to Technical Specifications2014-07-17017 July 2014 License Amendment Request to Move Linear Heat Generation Rate (LHGR) and Single Loop Operation LHGR Limit from Technical Requirements Manual to Technical Specifications NLS2013050, Submittal of Technical Specification Base Changes2013-04-25025 April 2013 Submittal of Technical Specification Base Changes ML12319A0552012-11-21021 November 2012 Correction to Amendment No. 242 Technical Specification (TS) and Safety Evaluation, Revise TSs to Implement a 24-Month Fuel Cycle and Adopt Technical Specification Task Force (TSTF)-493, Revision 4, Option a NLS2011093, Submittal of Technical Specification Bases Changes2011-10-14014 October 2011 Submittal of Technical Specification Bases Changes NLS2010029, Technical Specifications Bases Changes2010-04-15015 April 2010 Technical Specifications Bases Changes NLS2008091, Technical Specification Bases Changes for Time Period from 03/15/2007 Through 09/04/20082008-10-13013 October 2008 Technical Specification Bases Changes for Time Period from 03/15/2007 Through 09/04/2008 ML0830302442008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Appendix D, Technical Specification Changes NLS2008002, License Amendment Request to Revise Technical Specification 3.7.3, Reactor Equipment Cooling System2008-03-24024 March 2008 License Amendment Request to Revise Technical Specification 3.7.3, Reactor Equipment Cooling System NLS2008009, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448-A, Revision 3, Using the Consolidated Item Improvement Process2008-01-14014 January 2008 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448-A, Revision 3, Using the Consolidated Item Improvement Process ML0722803152007-08-10010 August 2007 Cooper - License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio NLS2007032, SSP-07/405-C, Rev. 1, Gardel BWR - Power Distribution Uncertainties, Enclosure 52007-05-11011 May 2007 SSP-07/405-C, Rev. 1, Gardel BWR - Power Distribution Uncertainties, Enclosure 5 NLS2007036, Technical Specification Bases Changes2007-04-30030 April 2007 Technical Specification Bases Changes NLS2006042, License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation2006-06-16016 June 2006 License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation ML0722803162006-05-0404 May 2006 Cooper, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Cycle 24 (GNF-A Report No. eDRF-0000-0046-6413), Enclosure 2 ML0612304672006-05-0202 May 2006 Technical Specifications Inoperability of Snubbers NLS2006010, Request for Exemption from Certain Requirements of 10 CFR 50, Appendix J and Corresponding Change to Technical Specifications 5.5.12, Primary Containment Leakage Rate Testing Program, Cooper Nuclear Station2006-03-15015 March 2006 Request for Exemption from Certain Requirements of 10 CFR 50, Appendix J and Corresponding Change to Technical Specifications 5.5.12, Primary Containment Leakage Rate Testing Program, Cooper Nuclear Station ML0601706232005-10-27027 October 2005 Tech Spec Pages for Amendment 212 Revision of the Required Channels Per Trip System for Primary and Secondary Containment Isolation and Control Room Emergency Filter System Instrumentation NLS2005061, Letter to Provide Changes to Plant Technical Specification Bases Implemented Without NRC Approval2005-07-25025 July 2005 Letter to Provide Changes to Plant Technical Specification Bases Implemented Without NRC Approval NLS2004088, Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports2004-11-22022 November 2004 Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports NLS2004122, License Amendment Request to Revise the Required Channels Per Trip System for Primary and Secondary Containment Isolation and Control Room Emergency Filter System Instrumentation2004-10-25025 October 2004 License Amendment Request to Revise the Required Channels Per Trip System for Primary and Secondary Containment Isolation and Control Room Emergency Filter System Instrumentation NLS2004099, License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio2004-10-25025 October 2004 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio ML0425100922004-09-0101 September 2004 Tech Spec Page for Amendment 206 Regarding LOCA Dose Methodology and Resolution of Remaining License Condition 2.C.(6) NLS2004007, License Amendment Request - One-Time Extension of Surveillance Requirements2004-01-30030 January 2004 License Amendment Request - One-Time Extension of Surveillance Requirements NLS2004005, License Amendment Request to Revise Technical Specification 3.4.9 Pressure Temperature (P/T) Curves Figures 3.4.9-1, 3.4.9-2, and 3.4.9-32004-01-29029 January 2004 License Amendment Request to Revise Technical Specification 3.4.9 Pressure Temperature (P/T) Curves Figures 3.4.9-1, 3.4.9-2, and 3.4.9-3 NLS2003098, Technical Specification Bases Changes2003-09-0505 September 2003 Technical Specification Bases Changes NLS2003066, License Amendment Request to Revise Technical Specification 3.5.1 to Incorporate TS Task Force (TSTF) 318 for One Low Pressure Coolant Injection (LPCI) Pump Inoperable in Each of the Two Emergency Core Cooling Systems (ECCS) Divisions2003-08-25025 August 2003 License Amendment Request to Revise Technical Specification 3.5.1 to Incorporate TS Task Force (TSTF) 318 for One Low Pressure Coolant Injection (LPCI) Pump Inoperable in Each of the Two Emergency Core Cooling Systems (ECCS) Divisions NLS2003077, License Amendment Request to Revise Technical Specification (TS) Surveillance Requirement (SR) 3.3.2.1.4 and TS Table 3.3.2.1-1 for Mathematical Symbols and Use of Allowable Values2003-08-25025 August 2003 License Amendment Request to Revise Technical Specification (TS) Surveillance Requirement (SR) 3.3.2.1.4 and TS Table 3.3.2.1-1 for Mathematical Symbols and Use of Allowable Values NLS2003022, License Amendment Request to Revise TS Surveillance Requirements for Locked, Sealed, or Secured Secondary Containment Isolation Valves2003-07-15015 July 2003 License Amendment Request to Revise TS Surveillance Requirements for Locked, Sealed, or Secured Secondary Containment Isolation Valves ML0320306102003-07-15015 July 2003 Issuance of License Amendment 200 Re. Changes to Title of Shift Supervisor to Shift Manaager and Changes Plant-Specific Titles to Generic Titles Consistent with TSTF-65, Rev. 1 NLS2002098, Application for Technical Specification Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process2002-09-26026 September 2002 Application for Technical Specification Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process ML0213004672002-05-0909 May 2002 Tech Spec Pages, Amendment No. 191 Correction of Errors in Technical Specification ML0204500312002-02-12012 February 2002 Technical Specification Page for Correction of Typographical Error in Amendment 178 2024-07-03
[Table view] Category:Bases Change
MONTHYEARNLS2024051, Supplement to the Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program2024-07-0303 July 2024 Supplement to the Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program NLS2024025, License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation2024-05-0909 May 2024 License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation NLS2023029, License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks2023-09-0606 September 2023 License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks NLS2023007, Technical Specification Bases Changes2023-04-17017 April 2023 Technical Specification Bases Changes NLS2021056, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2021-11-16016 November 2021 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2021015, (CNS) - Technical Specification Bases Changes2021-04-16016 April 2021 (CNS) - Technical Specification Bases Changes NLS2020004, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2020-04-0101 April 2020 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules NLS2020007, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process2020-04-0101 April 2020 Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process NLS2019020, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit Mcpr.2019-05-23023 May 2019 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit Mcpr. NLS2019022, Application for Technical Specifications Improvement to Eliminate Requirements for Hydrogen/Oxygen Monitors (TSTF-447, Rev. 1)2019-05-23023 May 2019 Application for Technical Specifications Improvement to Eliminate Requirements for Hydrogen/Oxygen Monitors (TSTF-447, Rev. 1) NLS2017033, Technical Specification Bases Changes2017-04-0707 April 2017 Technical Specification Bases Changes NLS2016002, Application to Revise Technical Specifications to Adopt TSTF 535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs.2016-03-11011 March 2016 Application to Revise Technical Specifications to Adopt TSTF 535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs. NLS2015040, Technical Specification Bases Changes2015-04-15015 April 2015 Technical Specification Bases Changes NLS2013050, Submittal of Technical Specification Base Changes2013-04-25025 April 2013 Submittal of Technical Specification Base Changes NLS2011093, Submittal of Technical Specification Bases Changes2011-10-14014 October 2011 Submittal of Technical Specification Bases Changes NLS2010029, Technical Specifications Bases Changes2010-04-15015 April 2010 Technical Specifications Bases Changes NLS2008091, Technical Specification Bases Changes for Time Period from 03/15/2007 Through 09/04/20082008-10-13013 October 2008 Technical Specification Bases Changes for Time Period from 03/15/2007 Through 09/04/2008 ML0830302442008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Appendix D, Technical Specification Changes NLS2007036, Technical Specification Bases Changes2007-04-30030 April 2007 Technical Specification Bases Changes NLS2006042, License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation2006-06-16016 June 2006 License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation NLS2006010, Request for Exemption from Certain Requirements of 10 CFR 50, Appendix J and Corresponding Change to Technical Specifications 5.5.12, Primary Containment Leakage Rate Testing Program, Cooper Nuclear Station2006-03-15015 March 2006 Request for Exemption from Certain Requirements of 10 CFR 50, Appendix J and Corresponding Change to Technical Specifications 5.5.12, Primary Containment Leakage Rate Testing Program, Cooper Nuclear Station NLS2005061, Letter to Provide Changes to Plant Technical Specification Bases Implemented Without NRC Approval2005-07-25025 July 2005 Letter to Provide Changes to Plant Technical Specification Bases Implemented Without NRC Approval NLS2003098, Technical Specification Bases Changes2003-09-0505 September 2003 Technical Specification Bases Changes NLS2002098, Application for Technical Specification Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process2002-09-26026 September 2002 Application for Technical Specification Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process 2024-07-03
[Table view] |
Text
H Nebraska Public Power District Always there when you need us 50.90 NLS2020007 April 1, 2020 Attention: Document Control Desk U.S. Nuclear Regulatory Commission
. Washington, D.C. 20555-0001
Subject:
Application to Revise Technical Specifications to Adopt TSTF-566, "Revise Actions for Inoperable RHR Shutdown Cooling Subsystems" using the Consolidated Line Item Improvement Process Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46
Dear Sir or Madam:
Pursuant to 10 CFR 50.90, Nebraska Public Power District (NPPD) is submitting a request for an amendment to the Technical Specifications (TS) for Cooper Nuclear Station (CNS).
NPPD requests adoption of TSTF-566, "Revise Actions for Inoperable RHR Shutdown Cooling Subsystems," which is an approved change to the Improved Standard Technical Specifications, into the CNS TS. The proposed amendment revises the TS actions applicable when a residual heat removal shutdown cooling subsystem is inoperable.
Attachment 1 provides a description and assessment of the proposed changes. Attachment 2 provides the existing TS pages marked to show the proposed changes. Attachment 3 provides revised (clean) TS pages. Attachment 4 provides existing TS Bases pages marked to show the proposed changes for information only.
Approval of the proposed amendment is requested by April 1, 2021. Once approved, the amendment shall be implemented within 60 days.
There are no regulatory commitments made in this submittal.
The proposed TS changes have been reviewed by the necessary safety review committees (Station Operations Review Committee and Safety Review and Audit Board). In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," a copy of this application, with attachments, is being provided to the designated State of Nebraska Official.
If you should have any questions regarding this submittal, please contact Linda Dewhirst, Regulatory Affairs and Compliance Manager, at (402) 825-5416.
COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402} 825-5211 www.nppd.com
NLS2020007 Page 2 of2 I declare under penalty of perjury that the foregoing is true and correct.
Executed On: -~1-+/-'-1:/~z_o_z_~__
Date Sincerely, l hn Dent, Jr.
Vice President and Chief Nuclear Officer
/dv Attachments: 1. Description and Assessment
- 2. Proposed Technical Specifications Changes (Mark-up)
- 3. Revised Technical Specifications Pages
- 4. Proposed Technical Specifications Bases Changes (Mark-up) -
Information Only cc: Regional Administrator w/ attachments USNRC - Region IV Cooper Project Manager w/ attachments USNRC - NRR Plant Licensing Branch IV Senior Resident Inspector w/ attachments USNRC-CNS Nebraska Health and Human Services w/ attachments Department of Regulation and Li censure NPG Distribution w/o attachments CNS Records w/ attachments
~--------
NLS2020007 Attachment 1 Page 1 of 4 Attachment 1 Description and Assessment Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46 1.0 Description 2.0 Assessment 2.1 Applicability of Safety Evaluation 2.2 Variations 3.0 Regulatory Analysis 3.1 No Significant Hazards Consideration Analysis 3 .2 Conclusion 4.0 Environmental Consideration
NLS2020007 Page 2 of 4
1.0 DESCRIPTION
Nebraska Public Power District (NPPD) requests adoption ofTSTF-566, "Revise Actions for Inoperable RHR Shutdown Cooling Subsystems," which is an approved change to the Improved Standard Technical Specifications, into the Cooper Nuclear Station (CNS) Technical Specifications (TS). The proposed amendment revises the TS actions applicable when a residual heat removal (RHR) shutdown cooling subsystem is inoperable.
2.0 ASSESSMENT 2.1 Applicability of Safety Evaluation NPPD has reviewed the safety evaluation for TSTF-566 provided to the Technical Specifications Task Force (TSTF) in a letter dated February 21, 2019. This review included a review of the Nuclear Regulatory Commission (NRC) staffs evaluation, as well as the information provided in TSTF-566. NPPD has concluded that the justifications presented in TSTF-566 and the safety evaluation prepared by the NRC staff are applicable to CNS and justify this amendment for the incorporation of the changes to the CNS TS.
2.2 Variations NPPD is proposing the following variations from the TS changes described in TSTF-566 or the applicable parts of the NRC staffs safety evaluation.
The CNS TS utilize different numbering than the Standard Technical Specifications on which TSTF-566 was based. Specifically:
- Specification 3.4.9, "RHR Shutdown Cooling System -Cold Shutdown" is Specification 3.4.8 in the CNS TS These differences are administrative and do not affect the applicability ofTSTF-566 to the CNS TS.
The traveler discusses the applicable regulatory requirement and guidance, including the 10 CFR 50, Appendix A, General Design Criteria (GDC). CNS was not licensed to the 10 CFR 50, Appendix A, GDC. The CNS equivalent of the GDC is located in Appendix F of the CNS Updated Safety Analysis Report. Specifically, the traveler refers to 10 CFR 50, Appendix A, Criterion 34. CNS does not have an equivalent draft GDC criterion. This difference does not alter the conclusion that the proposed change is applicable to CNS.
NLS2020007 Page 3 of 4
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration Analysis Nebraska Public Power District (NPPD) requests adoption ofTSTF-566, "Revise Actions for Inoperable RHR Shutdown Cooling Subsystems," which is an approved change to the Improved Standard Technical Specifications, into the Cooper Nuclear Station Technical Specifications (TS).
The proposed amendment revises the TS actions applicable when a residual heat removal (RHR) shutdown cooling subsystem is inoperable.
NPPD 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 The proposed change revises the actions to be taken when a RHR shutdown cooling subsystem is inoperable. The RHR System in the shutdown cooling mode performs the important safety function of removing decay heat from the reactor coolant system during shutdown. The RHR System in the shutdown cooling mode is not an initiator of any accident previously evaluated or assumed to mitigate any accident previously evaluated. The design and function of the RHR System are not affected by the proposed change.
Therefore, the proposed change does 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 change revises the actions to be taken when a RHR shutdown cooling subsystem is inoperable. The proposed change does not affect the design function or operation of the RHR shutdown cooling subsystems. No new equipment is being installed as a result of the proposed change. The proposed change only affects the actions taken when an RHR shutdown cooling subsystem is inoperable, so no new failure mechanisms are created.
NLS2020007 Page 4 of 4 Therefore, the proposed change does 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 change revises the actions to be taken when a RHR shutdown cooling subsystem is inoperable. The proposed change does not change any specific values or controlling parameters that define margin in the design or licensing basis. No safety limits are affected by the proposed change. The RHR System in the shutdown cooling mode removes decay heat from the reactor coolant system during shutdown. The proposed change does not affect any design or safety limits associated with the RHR System.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, NPPD concludes that the proposed change presents no 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.
3.2 Conclusion 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.
- 4. ENVIRONMENTAL CONSIDERATION The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change 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 change.
NLS2020007 Page 1 of 5 Attachment 2 Proposed Technical Specifications Changes (Mark-up)
Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46 Revised Pages 3.4-15 3.4-16 3.4-18 3.4-19
RHR Shutdown Cooling System - Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.
NOTES---------------------
- 1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
- 2. One RHR shutdown cooling subsystem may be inoperable for up to 2 liours for the performance of Surveillances.
APPLICABILITY: MODE 3, with reactor steam dome pressure less than the shutdown cooling permissive pressure.
ACTIONS
- -------------NOTE---------------
Separate Condition entry is allowed for each RHR shutdown cooling subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or two RHR shutdown A.1 lflitiate aetien te resteFe Iffilflediately cooling subsystems RHR sht:1tdert1fl eoolifl~
inoperable. s~esystel'ltEs~ te OPERABLE statt:1s.
All.In
,coRtii:iued)
Cooper 3.4-15 Amendment No. z6S-
RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (eeAtiFttJed) Verify an alternate method 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of decay heat removal is available for each B. Required Action 8.1 Initiate action inoperable RHR shutdown Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and associated cooling subsystem.
to restore RH R thereafter Completion Time of shutdown cooling Condition A not subsystem(s) to met. OPERABLE status. 24 l'iettFS Immediately No RHR shutdown cooling Initiate action to restore Immediately subsystem in operation. one RHR shutdown
. cooling subsystem or one AND recirculation pump to operation.
No recirculation pump in operation.
Verify reactor coolant 1 hourfrom circulation by an alternate discovery of no method. reactor coolant circulation Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter Monitor reactor coolant Once per hour temperature and pressure.
Cooper 3.4-16 Amendment No.~
RHR Shutdown Cooling System - Cold Shutdown 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS}
3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown LCO 3.4.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.
NOTES--------------
- 1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
- 2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the performance of Surveillances.
APPLICABILITY: MODE 4.
ACTIONS
NOTE --------
Separate Condition entry is allowed for each shutdown cooling subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or two RHR shutdown A.1 Verify an alternate method 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cooling subsystems of decay heat removal is inoperable. available for each ANO inoperable RHR shutdown cooling subsystem. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter B. Required Action and associated 8.1 Initiate action to Completion Time of restore RHR shutdown Condition A not met. cooling subsystem(s) to Immediately OPERABLE status.
Cooper 3.4-18 Amendment No.~
RHR Shutdown Cooling System - Cold Shutdown 3.4.8 ACTIONS {continued)
CONDITION REQUIRED ACTION COMPLETION TIME
--8:- No RHR shutdown cooling .4- Verify reactor coolant 1 hourfrom subsystem in operation. circulating by an alternate discovery of no method. reactor AND coolant circulation 1
No recirculation pump in operation.
Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter
--8-:2- Monitor reactor coolant Once per hour
\ temperature.
....i........ :=""IIC.2 Ii----- ----=- -------
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one RHR shutdown cooling subsystem or In accordance with recirculation pump Is operating. the Surveillance Frequency Control Program Cooper 3.4-19 Amendment No. -265-
NLS2020007 Page 1 of 5 Attachment 3 Revised Technical Specifications Pages Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46 Revised Pages 3.4-15 3.4-16 3.4-18 3.4-19
RHR Shutdown Cooling System - Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS)
. 3.4. 7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.
NOTES-------------------------------------------
- 1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
- 2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the performance of Surveillances.
APPLICABILITY: MODE 3, with reactor steam dome pressure less than the shutdown cooling permissive pressure.
ACTIONS
NOTE------------------------------------------------------------
Separate Condition entry is allowed for each RHR shutdown cooling subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or two RHR shutdown A.1 Verify an alternate method 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cooling subsystems of decay heat removal is inoperable. available for each inoperable RHR shutdown cooling subsystem. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter (continued)
Cooper 3.4-15 Amendment No.
RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Initiate action to restore Immediately associated Completion Time RHR shutdown cooling of Condition A not met. subsystem(s) to OPERABLE status.
C. No RHR shutdown cooling C.1 Initiate action to restore Immediately subsystem in operation. one RHR shutdown cooling subsystem or one AND recirculation pump to operation.
No recirculation pump in operation. AND C.2 Verify reactor coolant 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from circulation by an alternate discovery of no method. reactor coolant circulation AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND C.3 Monitor reactor coolant Once per hour temperature and pressure.
Cooper 3.4-16 Amendment No.
RHR Shutdown Cooling System - Cold Shutdown 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown LCO 3.4.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.
NOTES-------------------------------------------
- 1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
- 2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the performance of Surveillances.
APPLICABILITY: MODE 4.
ACTIONS
*----------------------NOTE-----------------------------------------------------------
Separate Condition entry is allowed for each shutdown cooling subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A One or two RHR shutdown A.1 Verify.an alternate method 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cooling subsystems of decay heat removal is inoperable. available for each AND inoperable RHR shutdown cooling subsystem. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter B. Required Action and 8.1 Initiate action to restore
(continued)
Cooper 3.4-18 Amendment No.
RHR Shutdown Cooling System - Cold Shutdown 3.4.8 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. No RHR shutdown cooling C. 1 Verify reactor coolant 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from subsystem in operation. circulating by an alternate discovery of no method. reactor AND coolant circulation No recirculation pump in AND operation.
Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND C.2 Monitor reactor coolant Once per hour temperature.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one RHR shutdown cooling subsystem or In accordance with recirculation pump is operating. the Surveillance Frequency Control Program Cooper 3.4-19 Amendment No.
NLS2020007 Page 1 of7 Attachment 4 Proposed Technical Specifications Bases Changes (Mark-up) -
Information Only Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46 Revised Pages B 3.4-36 B 3.4-37 B 3.4-42 B 3.9-24 B 3.9-29 Note: Attachment includes page of Bases Inserts
i--
1 NLS2020007 Attachment 4 Page 2 of7 Bases Inserts Insert 1 (B 3.4.7 Required Action A.l)
Furthermore, verification of the functional availability of these alternate method(s) must be reconfirmed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter. This will provide assurance of continued heat removal capability.
Insert 2 (B 3.4.7 and B 3.4.8 new Required Action B.1)
If the required alternate method(s) of decay heat removal cannot be verified within one hour, immediate action must be taken to restore the inoperable RHR shutdown cooling subsystem(s) to operable status. The Required Action will restore redundant decay heat removal paths. The immediate Completion Time reflects the importance of maintaining the availability of two paths for heat removal.
Insert 3 (B 3.9.7 and B 3.9.8 Required Action A.l)
The required cooling capacity of the alternate method should be sufficient to maintain or reduce temperature. Decay heat removal by ambient losses can be considered as, or contributing to, the alternate method capability. Alternate methods that can be used include (but are not limited to) the Spent Fuel Pool Cooling System, the Reactor Water Cleanup System, or an inoperable but functional RHR shutdown cooling subsystem.
RHR Shutdown Cooling System-Hot Shutdown B 3.4.7 BASES ACTIONS
\
A Note has been provided to modify the ACTIONS related to RHR shutdown cooling subsystems. Section 1.3, Completion Times, specifies once a Condition has been entered, subsequent divisions, subsystems, components or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition. Section 1.3 also specifies Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for inoperable shutdown cooling subsystems provide appropriate compensatory measures for separate inoperable shutdown cooling subsystems. As such, a Note has been provided that allows separate Condition entry for each inoperable RHR shutdown cooling subsystem.
A.1, A.2, anel A.3 With one required RHR shutdown cooling subsystem inoperable for decay heat removal, except as permitted by LCO Note 2, the inopei:ael~
sybsystem mi.n;:;t ber:ester:ed te OPERA.BU: sta&is withe1:1t eelay. In this sensitien, the r:smaining O~ERABbE s1:1bsystaFR saA pFO'Jiae tl=le nesm;sary desay heat FOmoval. Tho overall reliability is reduced, ha'll*ve'Jef; because a single failure in the OPERABLE subsystem could result in reduced RHR shutdown cooling capability. Therefore, an alternate method of decay heat removal must be provided.
With both RHR shutdown cooling subsystems inoperable, an alternate method of decay heat removal must be provided in addition to that provided for the initial RHR shutdown cooling subsystem inoperability.
This re-establishes backup decay heat removal capabilities, similar to the requirements of the LCO. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on the decay heat removal function and the probability of a loss of the available.--_ _ ___,
decay heat removal capabilities. -< ![INSERT 1] I sufficient to The required cooling capacity of the alternate method should be ensured by '.°'Orifying (by ealeulation or deFAanstratien) its eapabilit)* to maintain or reduce temperature. Decay heat removal by ambient losses can be considered as, or contributing to, the alternate method capability.
Alternate methods that can be used include (but are not limited to) the Condensate/Main Steam Systems, the Reactor Water Cleanup System,
~ a combination of an ECCS pump and a safetv/relief valve... .... ,,
, or an inoperable but functional RHR Hows\rer, d1:10 te the potentially rsel1:1oeel FOliability of the alternate shutdown cooling ~ Y heammsval, it is also me;1:1ir0el te meh,1se tho master system. soolimt tompemt1:1m te the point 'NReFS MODE 4 iG entorsel.
[INSERT 2]
Cooper B 3.4-36 1211e119 I
RHR Shutdown Cooling System-Hot Shutdown B 3.4.7 BASES ACTIONS (continued)
C.1, C.2, and C.3 B.1, 8.2. and B.3 With no RHR shutdown cooling subsystem and no recirculation pump in operation, except as permitted by LCO Note 1, reactor coolant circulation by the RHR shutdown cooling subsystem or recirculation pump must be restored without delay.
Until RHR or recirculation pump operation is re-established, an alternate method of reactor coolant circulation must be placed into service. This will provide the necessary circulation for monitoring coolant temperature.
The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on the coolant circulation function and is modified such that the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is applicable separately for each occurrence involving a loss of coolant circulation. Furthermore, verification of the functioning of the alternate method must be reconfirmed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. This will provide assurance of continued temperature monitoring capability.
During the period when the reactor cool~nt is being circulated by an alternate method (other than by the required RHR shutdown cooling subsystem or recirculation pump), the reactor coolant temperature and pressure must be periodically monitored to ensure proper function of the alternate method. The once per hour Completion Time is deemed appropriate.
SURVEILLAN CE REQUIREMENTS SR 3.4.7.1 This Surveillance verifies that one RHR shutdown cooling subsystem or recirculation pump is in operation and circulating reactor coolant. The required flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
This Surveillance is modified by a Note allowing sufficient time to align the RHR System for shutdown cooling operation after clearing the pressure interlock that isolates the system, or for placing a recirculation pump in operation. The Note takes exception to the requirements of the Surveillance being met (i.e., forced coolant circulation is not required for this initial 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period), which also allows entry into the Applicability of this Specification in accordance with SR 3.0.4 since the Surveillance will not be "not met" at the time of entry into the Applicability.
Cooper B 3.4-37 12119119 I
RHR Shutdown Cooling Syst~~~Cold Shutdown
..- B 3.4.8 BASES ACTIONS A.:.l (continued)
Therefore, an alternate method of decay heat removal must be provided. With both RHR shutdown cooling subsystems inoperable, an alternate method of decay heat removal must be provided in addition to that provided 'for the initial RHR shutdown cooling subsystem inoperability. This re-establishes backup decay heat removal capabilities, similar to the requirements of the LCO. The l hour Completion Time is based on the decay heat removal function and the probability of a loss of the available decay heat removal capabilities. Furthermore, verification of the functional availability of these alternate method{s) must be reconfirmed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter. This will provide assurance of continued heat removal capability.
The required cooling capacity of the alternate method should
~ . be eRsureEI l3:Y verifyiR§ (l:ly ealculatieR er ElemeRstratieR)
~ its Gapability to maintain or reduce temperature. Decay heat removal by ambient losses can be considered as, or contributing to, the alternate method capability. Alternate methods that can be used include {but are not limited to) the Reactor Water Cleanup S~ystem -aft&-a combination of an
~ ECCS pump and a safety/relief v ve r-------------,
~ ~ , , or an inoperable but
:?" IL 1 aRe B.2 functional RHR shutdown
[ cooling subsystem
!C.1 and C.2 With no RHR shutdown cooling subsystem and no recirculation pump in operation, except as permitted by LCO Note 1, and until RHR or recirculation pump operation is re-established, an alternate method of reactor coolant circulation must be placed into service. This will provide the necessary circulation for monitoring coolant temperature. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on the coolant circulation function and is modified such that the I hour is applicable separately for each occurrence involving a loss of coolant circulation. Furthermore, verification of the functioning of the alternate method must be reconfirmed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. This will provide assurance of continued temperature monitoring capability.
During the period when the reactor coolant is being circulated by an alternate method (other than by the required RHR shutdown cooling subsystem or recirculation pump), the reactor coolant temperature and pressure must be (continued)
Cooper B 3.4-42 Revisia~ 9
RHR-ttigh Water Level B 3.9.7 BASES ACTIONS A.l (continued) heat from the reactor core. However, the overall reliability is reduced because loss of water level could result in reduced decay heat removal capability. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on decay heat removal function and the probability of a loss of the available decay heat removal capabilities. Furthermore, verification of the functional availability of the alternate method must be reconfirmed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter. This will ensure continued heat removal capability.
Alternate decay heat removal methods are available to the operators for review and preplanning in the unit Operating Procedures. T~e req1:1ired caaliA§ ca13acity af the alterAate met Ras sha1:1hi be 0Rs1:1red b;Y veri fyi R§ ( by cal c1:1l at i aR er aeffionstra.tion) its eap-ability to mailitaiii or 1ed~e@
tem13erat1:1re. Far exam13l e, tk is may i Acl 1:1cle tke use af H ~
~ S13eRt Fwel Peal Gaal iR§ Systeffl aRa tl:ie Reactar Water Cl eaR1:113
£ystem, a13eratiR§ wit~ tRe regeRerative ~eat cxchaAger by13assed er iR cembiRatiaR with the CeRtral Rea Drive System or (QRQ(Ul&aie System... The method used to remove the decay heat should be the most prudent choice based on station conditions.
8.1, 8.2, B.3, and B.4 If no RHR shutdown cooling subsystem is OPERABLE and an alternate method of decay heat removal is not available in accordance with Required Action A.l, actions shall be taken immediately to suspend operations involving an increase in reactor decay heat load by suspending loading of irradiated fuel assemblies into the RPV.
Additional actions are required to minimize any potential fission product release to the environment. This includes ensuring secondary containment is OPERABLE; one standby gas treatment subsystem is OPERABLE; and secondary containment isolation capability is available in each associated penetration flow path not isolated that is assumed to be isolated to mitigate radioactive releases {i.e., one secondary containment isolation valve and associated instrumentation are OPERABLE or other acceptable administrative cont~ols to assure isolation capability.
These administrative controls consist of stationing an (continued)
Cooper B 3.9-24 RevisiaA O
RHR~Low Water Level B 3.9.8 BASES ACTIONS A.1 (continued}
LCO. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on the decay heat removal function and the probability of a loss of the available decay heat removal capabilities. Furthermore, verification of the functional availability of this alternate method must be reconfirmed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter. This will ensure continued heat removal capability.
Alternate decay heat removal methods are available to the operators for review and preplanning in the unit Operating Procedures. +ltt: required eeel i Ag capacity af the alterAate
![INSERT 3] methaa shaYlel ae eRs1:noea l:Jy \,'el"ifyiRg (l:Jy calc1:.1latieA er ElemaAstratisR) its ca~aeity ts maiAtaiflSr iceel1:.1ce tem~el"at1:.1re. Fsr exam~le, this may iRcl1:.1de tRe ~se ef tRe SpeAt F~el Peel CeeliA§ System aAa the Reacter Water GleaRUf.)
Systeffl, ef.)erati Ag \~i th Uie re§eiterati ve heat e~ckafl~
byf.)a-s-s-ea er i 1, cemai 1,ati Sl'I with the CaRtral Rael Drive System--
er CsRseRsate ~ystem, The method used to remove decay heat should be the most prudent choice based on station conditions.
B.1, B.2, and 8.3 With the required decay heat removal subsystem(s} inoperable and the required alternate method(s} of decay heat removal not available in accordance with Required Action A.l, additional actions are required to minimize any potential fission product release to the environment. This includes ensuring secondary containment is OPERABLE; one standby gas treatment subsystem is OPERABLE; and secondary containment isolation capability is available in each associated penetration flow path not isolated that is assumed to be isolated to mitigate radioactive releases (i.e., one secondary containment isolation valve and associated instrumentation are OPERABLE or other acceptable administrative controls to assure isolation capability.
These administrative controls consist of stationing an operator, who is in continuous communication with the control room, at the controls of the isolation device. In this way, the penetration can be rapidly isolated when a need for secondary containment is indicated.} This may be performed as an administrative check, by examining logs or (continued}
Cooper B 3.9-29 Revisiefl 0