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Category:Letter type:NLS
MONTHYEARNLS2024006, 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 NLS2022035, Evacuation Time Estimate Report for Cooper Nuclear Station2022-08-16016 August 2022 Evacuation Time Estimate Report for Cooper Nuclear Station NLS2022031, Licensee Guarantees of Payment of Deferred Premiums2022-07-19019 July 2022 Licensee Guarantees of Payment of Deferred Premiums 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 NLS2022025, Nebraska Public Power District Letter (NLS2022010) to U.S. Nuclear Regulatory Commission Dated April 5, 2022, Annual Report of Individual Exposure Monitoring2022-06-0606 June 2022 Nebraska Public Power District Letter (NLS2022010) to U.S. Nuclear Regulatory Commission Dated April 5, 2022, Annual Report of Individual Exposure Monitoring NLS2022016, Annual Radiological Environmental Report2022-05-10010 May 2022 Annual Radiological Environmental Report NLS2022020, Nebraska Public Power District, Cooper Nuclear Station, 2021 Financial Report2022-05-0202 May 2022 Nebraska Public Power District, Cooper Nuclear Station, 2021 Financial Report NLS2022014, Annual Radioactive Effluent Release Report2022-04-27027 April 2022 Annual Radioactive Effluent Release Report NLS2022010, Annual Report of Individual Exposure Monitoring2022-04-0505 April 2022 Annual Report of Individual Exposure Monitoring NLS2022009, Property Insurance Coverage2022-03-23023 March 2022 Property Insurance Coverage NLS2022011, Preparation and Scheduling of Operator Licensing Examinations2022-03-18018 March 2022 Preparation and Scheduling of Operator Licensing Examinations NLS2022004, Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Relief Request RR5-01, Revision 12022-02-0707 February 2022 Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Relief Request RR5-01, Revision 1 NLS2022003, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20212022-01-20020 January 2022 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2021 NLS2021067, ISFSI - Independent Spent Fuel Storage Installation Decommissioning Funding Plan2021-12-16016 December 2021 ISFSI - Independent Spent Fuel Storage Installation Decommissioning Funding Plan NLS2021069, Withdrawal of Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2021-12-15015 December 2021 Withdrawal of Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2021066, Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Alternative Request RI5-02, Revision 32021-12-10010 December 2021 Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Alternative Request RI5-02, Revision 3 NLS2021065, Clarification of Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-012021-12-0606 December 2021 Clarification of Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-01 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 2024-01-25
[Table view] Category:Technical Specification
MONTHYEARNLS2023029, 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 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 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 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 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 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 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 2023-09-06
[Table view] Category:Amendment
MONTHYEARNLS2023018, 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 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 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 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 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 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 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 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 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 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 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 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 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 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 2023-05-03
[Table view] |
Text
H Nebraska Public Power District
Alwllys there when you need us" 50.90 NLS2023018 May 3, 2023 Attention: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Subject:
Application to Revise Technical Specifications to Adopt TSTF-580, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling" 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.
NPPD requests adoption ofTSTF-58 0, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling." The proposed change provides a Technical Specifications exception to entering Mode 4 if both required Residual Heat Removal shutdown cooling subsystems are inoperable. provides a description and assessment of the proposed changes. Attachment 2 provides the existing TS pages marked up to show the proposed changes. Attachment 3 provides revised (clean) TS pages. Attachment 4 provides existing TS Bases pages marked up to show the associated TS Bases changes and is provided for information only.
Approval of the proposed amendment is requested by May 3, 2024. Once approved, the amendmen t 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 72676 648A Ave/ P.O. Box 98 / Brownville, NE 68321 http://www.nppd.com
NLS2023018 Page 2 of2 I declare under penalty of perjury that the foregoing is true and correct.
Executed On: ? / 3,/ ~o 2-3 Date Sincerely, Khalil Dia Site Vice President
/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/ attachments CNS Records w/ attachments
NLS2023018 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 Variation 3.0 Regulatory Analysis 3.1 No Significant Hazards Consideration Analysis 3.2 Conclusion 4.0 Environmental Evaluation
NLS2023018 Attachment 1 Page 2 of 4
1.0 DESCRIPTION
Nebraska Public Power District (NPPD) requests adoption ofTSTF-580, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling." The proposed change provides a Technical Specifications (TS) exception to entering Mode 4 if both required Residual Heat Removal (RHR) shutdown cooling subsystems are inoperable.
2.0 ASSESSMENT 2.1 Applicability of Safety Evaluation Nebraska Public Power District (NPPD) has reviewed the safety evaluation for TSTF-580 provided to the Technical Specifications Task Force (TSTF) in a letter dated July 11, 2021. This review included a review of the Nuclear Regulatory Commission (NRC) staffs evaluation, as well as the information provided in TSTF-580. NPPD has concluded that the justifications presented in TSTF-580 and the safety evaluation prepared by the NRC staff are applicable to Cooper Nuclear Station (CNS) and justify this amendment for the incorporation of the changes to the CNS TS.
Adoption ofTSTF-566-A, "Revise Actions for Inoperable RHR Shutdown Cooling Subsystems,"
was approved by the NRC for CNS on December 2, 2020.
2.2 Variation NPPD is proposing the following variation from the TS changes described in TSTF-580 or the applicable parts of the NRC staffs safety evaluation. This variation does not affect the applicability ofTSTF-580 or the NRC staffs safety evaluation to the proposed license amendment.
The CNS TS utilize different numbering than the Standard Technical Specifications (STS) on which TSTF-580 was based. Specifically, CNS equivalent TS are numbered as TS 3.4.7 instead of the STS numbering of TS 3.4.8. This difference is administrative and does not affect the applicability of TSTF-580 to the CNS TS.
3.0 REGULATORY ANALYSIS
3 .1 No Significant Hazards Consideration Analysis Nebraska Public Power District (NPPD) requests adoption ofTSTF-580, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling." The proposed change provides a Technical Specifications (TS) exception to entering MODE 4 if both required Residual Heat Removal (RHR) shutdown cooling subsystems are inoperable.
NLS2023018 Page 3 of 4 NPPD has evaluated if 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 provides a TS exception to entering Mode 4 if both required RHR shutdown cooling subsystems are 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.
The proposed change would also exempt entering Mode 4 if both required RHR shutdown cooling subsystems are inoperable and other operating modes of the RHR System are inoperable, such as Low Pressure Core Injection and RHR suppression pool cooling, and both subsystems of the support system for the RHR System heat exchangers, the RHR Service Water (RHRSW) System, are inoperable. The TS for those RHR operating modes and the RHRSW System require entering Mode 4 when both required subsystems are inoperable. Those operating modes and systems are not initiators to any accident previously evaluated but are used to mitigate the consequences of an accident previously evaluated.
However, the consequences of an accident previously evaluated resulting from remaining in Mode 3 versus Mode 4 when RHR shutdown cooling subsystems are inoperable are not significantly increased because there would be no dependable method to remove post-accident decay heat in Mode 4 if both required RHR shutdown cooling subsystems are inoperable.
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 provides a TS exception to entering Mode 4 if both required RHR shutdown cooling subsystems are inoperable. The proposed change does not affect the design function or operation of the RHR System or the RHRSW System. No new equipment is being installed as a result of the proposed change. The proposed change affects the action taken when both required RHR shutdown cooling subsystems are inoperable, so no new failure mechanisms are created.
NLS2023018 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 provides a TS exception to entering Mode 4 if both required RHR shutdown cooling subsystems are 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 proposed change applies when both required RHR shutdown cooling subsystems are inoperable, so no design or safety limits associated with the operation of the RHR System are affected.
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. ENVIRONMENTALEVALUATION 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 10 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 effluents 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.
NLS2023018 Page 1 of 3 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
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
--------------------NO TE------------------------------------------------------------
Se para te Condition entry is allowed for each RHR shutdown cooling subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A. One ef--twerequired RHR 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 /> shutdown cooling of decay heat removal is subsystems inoperable. available feF eael=l AND iA9J39Faele RJ==IR SRtJtee\&JA eeeliAg stJesystem. 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 B.1 Initiate action to restore Immediately associated Completion Time RHR shutdown cooling of Condition A not met. subsystem~ to OPERABLE status.
( continued)
Cooper 3.4-15 Amendment No.
RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Two reguired RHR C.1 Verif~ an alternate method 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> shutdown cooling of deca~ heat removal is subs~stems inoQerable. available for each AND inoQerable RHR shutdown cooling subs~stem. Once Qer 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter D. Reguired Action and ----------------------NOTE------------------
associated ComQletion Time LCO 3.0.3 and all other LCO of Condition C not met. Reguired Actions reguiring a MODE change to MODE 4 ma~ be sus1;2ended until one RHR shutdown cooling subs~stem is restored to OPERABLE status.
D.1 Initiate action to restore Immediate!~
one RHR shutdown cooling subs~stem to OPERABLE status.
G!;.No RHR shutdown cooling Gl~.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 GE.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 GE.3
- Monitor reactor coolant Once per hour temperature and pressure.
Cooper 3.4-16 Amendment No.
NLS2023018 Page 1 of 3 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
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------------------------------------------------------------
Se para te Condition entry is allowed for each RHR shutdown cooling subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A. One required RHR 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 /> shutdown cooling of decay heat removal is subsystem inoperable. available. AND 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 B.1 Initiate action to restore Immediately associated Completion Time RHR shutdown cooling of Condition A not met. subsystem to OPERABLE status.
(continued)
Cooper 3.4-15 Amendment No.
RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS ( continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Two required RHR C.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 /> shutdown cooling of decay heat removal is subsystems 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 D. Required Action and ----------------------NOTE------------------
associated Completion Time LCO 3.0.3 and all other LCO of Condition C not met. Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.
D.1 Initiate action to restore Immediately one RHR shutdown cooling subsystem to OPERABLE status.
E. No RHR shutdown cooling E.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 E.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 E.3 Monitor reactor coolant Once per hour temperature and pressure.
Cooper 3.4-16 Amendment No.
NLS2023018 Page 1 of 4 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 3.4-38
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.
With one required RHR shutdown cooling subsystem inoperable for decay heat removal, except as permitted by LCO Note 2, the overall reliability is reduced, 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 shutdovm 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. 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 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 Condensate/Main Steam Systems, the Reactor Water Cleanup System, a combination of an ECCS pump and a safety/relief valve, or an inoperable but functional RHR shutdown cooling system.
Cooper B 3.4-36 01/06/21
RHR Shutdown Cooling System-Hot Shutdown B 3.4.7 BASES ACTIONS (continued)
If the required alternate methodfs-1 of decay heat removal cannot be verified within one hour, immediate action must be taken to restore the inoperable RHR shutdown cooling subsystemfs-1 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.
C. 1 With both required 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. 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 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 Reactor Water Cleanup System. or an inoperable but functional RHR shutdown cooling subsystem.
D.1 If the required alternate methods of decay heat removal cannot be verified within one hour. immediate action must be taken to restore at least one RHR shutdown cooling subsystem to OPERABLE status. The immediate Completion Time reflects the importance of restoring a method of heat removal.
Required Action D.1 is modified by a Note indicating that all required MODE changes to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status. In this case. LCO 3.0.3 and other Required Actions directing entry into MODE 4 could force the unit into a less safe condition in which there may be no adequate means to remove decay heat. It is more appropriate to allow the restoration of one of the RHR shutdown cooling subsystems before Cooper B 3.4-37 01/06/21
RHR Shutdown Cooling System-Hot Shutdown B 3.4.7 BASES ACTIONS ( continued) requiring entry into a condition in which that subsystem would be needed and exiting a condition where other sources of cooling are available.
When at least one RHR subsystem is restored to OPERABLE status. the Completion Times of LCO 3.0.3 or other Required Actions resume at the point at which they were suspended.
GE.1, GE.2, and GE.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 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 periodically monitored to ensure proper function of the alternate method. The once per hour Completion Time is deemed appropriate.
SURVEILLANCE 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.
Cooper B 3.4-38 01/06/21