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Category:Letter type:GO
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan GO2-24-003, Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing2024-01-29029 January 2024 Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing GO2-24-005, Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-1702024-01-0808 January 2024 Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-170 GO2-23-136, Guarantee of Payment of Deferred Premium2023-12-20020 December 2023 Guarantee of Payment of Deferred Premium GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023 Notice of Readiness for Supplemental Inspection GO2-23-130, Reply to a Notice of Violation; EA-23-0542023-12-14014 December 2023 Reply to a Notice of Violation; EA-23-054 GO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-126, Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-012023-11-28028 November 2023 Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-01 GO2-23-121, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-27027 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation GO2-23-097, In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26)2023-09-0606 September 2023 In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26) GO2-23-100, Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication2023-08-31031 August 2023 Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication GO2-23-056, Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2023-08-29029 August 2023 Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling GO2-23-093, Supplement to Reply to a Notice of Violation: EA-21-1702023-07-27027 July 2023 Supplement to Reply to a Notice of Violation: EA-21-170 GO2-23-068, Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation2023-07-19019 July 2023 Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation GO2-23-090, Reply to a Notice of Violation2023-07-12012 July 2023 Reply to a Notice of Violation GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report GO2-23-055, Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications GO2-23-053, 2022 Annual Environmental Operating Report2023-04-26026 April 2023 2022 Annual Environmental Operating Report GO2-23-057, 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 2022 Annual Radioactive Effluent Release Report GO2-23-012, Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2023-03-27027 March 2023 Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-041, Generation Station - Level of Financial Protection - Annual Reporting Requirement2023-03-15015 March 2023 Generation Station - Level of Financial Protection - Annual Reporting Requirement GO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023 Plant Decommissioning Fund Status Report GO2-23-034, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462023-03-13013 March 2023 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 GO2-23-035, Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-03-0909 March 2023 Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling GO2-23-019, Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-012023-02-0808 February 2023 Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-01 GO2-22-131, Guarantee of Payment of Deferred Premium2022-12-19019 December 2022 Guarantee of Payment of Deferred Premium GO2-22-122, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-11-28028 November 2022 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-076, Status of License Renewal Commitments2022-10-31031 October 2022 Status of License Renewal Commitments GO2-22-110, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor2022-10-17017 October 2022 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor GO2-22-096, Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-10-0404 October 2022 Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-085, Docket No. 50-397, Evacuation Time Estimate Analysis2022-08-30030 August 2022 Docket No. 50-397, Evacuation Time Estimate Analysis GO2-22-075, Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves2022-07-11011 July 2022 Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves GO2-22-072, Summary of Changes and Analysis for Revision 57 of PPM 13.14.4 - Emergency Equipment Maintenance and Testing2022-07-11011 July 2022 Summary of Changes and Analysis for Revision 57 of PPM 13.14.4 - Emergency Equipment Maintenance and Testing GO2-22-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process2022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process GO2-22-062, Registration of Spent Fuel Cask Use2022-05-19019 May 2022 Registration of Spent Fuel Cask Use GO2-22-049, Supplement to Licensing Amendment Request to Adopt 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Rectors2022-05-10010 May 2022 Supplement to Licensing Amendment Request to Adopt 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Rectors GO2-22-054, Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report2022-05-0909 May 2022 Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report GO2-22-056, Registration of Spent Fuel Cask Use2022-04-21021 April 2022 Registration of Spent Fuel Cask Use GO2-22-055, 2021 Annual Environmental Operating Report2022-04-20020 April 2022 2021 Annual Environmental Operating Report GO2-22-048, 2021 Annual Radioactive Effluent Release Report2022-04-15015 April 2022 2021 Annual Radioactive Effluent Release Report GO2-22-045, Registration of Spent Fuel Cask Use2022-04-0606 April 2022 Registration of Spent Fuel Cask Use GO2-22-044, Level of Financial Protection - Annual Reporting Requirement2022-03-21021 March 2022 Level of Financial Protection - Annual Reporting Requirement GO2-22-038, Docket No. 50-397, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462022-03-0909 March 2022 Docket No. 50-397, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 GO2-22-031, Response to Audit Plan and Online Reference Portal Request2022-02-15015 February 2022 Response to Audit Plan and Online Reference Portal Request GO2-22-011, Docket No. 72-35; Independent Spent Fuel Storage Installation, 2021 Annual Effluent Release Report2022-02-0808 February 2022 Docket No. 72-35; Independent Spent Fuel Storage Installation, 2021 Annual Effluent Release Report GO2-22-001, License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-02-0303 February 2022 License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-012, Independent Spent Fuel Storage Installation - Biennial 50.59/72.48 Report2022-01-24024 January 2022 Independent Spent Fuel Storage Installation - Biennial 50.59/72.48 Report 2024-01-08
[Table view] Category:Technical Specification
MONTHYEARGO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications GO2-23-035, Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-03-0909 March 2023 Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling GO2-22-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process2022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process GO2-21-016, License Amendment Request to Change Technical Specification 3.4.11 Reactor Coolant System Pressure and Temperature Limits2021-10-13013 October 2021 License Amendment Request to Change Technical Specification 3.4.11 Reactor Coolant System Pressure and Temperature Limits GO2-20-004, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR2020-01-27027 January 2020 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR ML19343C0352019-12-0505 December 2019 Rev. 111 to Licensee Controlled Specifications Manual - Part 2 of 2 GO2-19-098, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2019-09-12012 September 2019 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules GO2-19-123, Supplemental Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems-Operating2019-08-19019 August 2019 Supplemental Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems-Operating GO2-19-119, Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating2019-08-15015 August 2019 Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating ML17355A6562017-12-21021 December 2017 Technical Specification Bases GO2-17-181, License Amendment Request to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-12-12012 December 2017 License Amendment Request to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements GO2-17-194, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-11-15015 November 2017 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control GO2-17-022, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-522 Revision 02017-01-19019 January 2017 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-522 Revision 0 GO2-16-119, License Amendment Request for One-Time 7 Day Extension of Completion Time for TS Condition 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A2016-11-0808 November 2016 License Amendment Request for One-Time 7 Day Extension of Completion Time for TS Condition 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A GO2-16-086, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 32016-07-14014 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3 GO2-16-096, License Amendment Request to Revise Operating License and Technical Specifications for Measurement Uncertainty Recapture Power Uprate2016-06-28028 June 2016 License Amendment Request to Revise Operating License and Technical Specifications for Measurement Uncertainty Recapture Power Uprate ML15355A4812015-12-21021 December 2015 Revision 87 to Technical Specification Bases GO2-15-070, Application for Technical Specification Change (TSTF-427) to Add LCO 3.0.9 on the Unavailability of Barriers Using the Consolidated Line Item Improvement Process2015-09-0202 September 2015 Application for Technical Specification Change (TSTF-427) to Add LCO 3.0.9 on the Unavailability of Barriers Using the Consolidated Line Item Improvement Process GO2-15-108, Provides Affected Technical Specification Pages Supporting License Amendment Request for Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-423, Revision 1, Using the Consolidated Line Item Improvement Process2015-08-11011 August 2015 Provides Affected Technical Specification Pages Supporting License Amendment Request for Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-423, Revision 1, Using the Consolidated Line Item Improvement Process GO2-15-075, Exigent License Amendment Request - Extension of Implementation Period for Amendment 232 Changing Technical Specification Table 3.3.1.1-1 Function 7 Scram Discharge Volume Water Level-High.2015-05-15015 May 2015 Exigent License Amendment Request - Extension of Implementation Period for Amendment 232 Changing Technical Specification Table 3.3.1.1-1 Function 7 Scram Discharge Volume Water Level-High. GO2-15-007, License Amendment Request for Adoption of Technical Specification Task Force Traveler-425, Revision 32015-03-17017 March 2015 License Amendment Request for Adoption of Technical Specification Task Force Traveler-425, Revision 3 GO2-14-139, Attachment 6 - GNF-001N8896-R3-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Columbia Cycle 232014-10-31031 October 2014 Attachment 6 - GNF-001N8896-R3-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Columbia Cycle 23 GO2-14-126, License Amendment Request to Revise Technical Specification Surveillance Requirement for the Ultimate Heat Sink2014-08-22022 August 2014 License Amendment Request to Revise Technical Specification Surveillance Requirement for the Ultimate Heat Sink ML14010A0302014-02-11011 February 2014 Issuance of Amendment No. 227, Request to Adopt Technical Specification Task Force (TSTF)-477, Revision 3, Adding an Action Statement for Two Inoperable Control Room Air Conditioning Subsystem ML14010A2902013-12-30030 December 2013 Columbia, 10 CFR 50.71 Maintenance of Records Licensing Basis Document Update ML13247A6592013-07-25025 July 2013 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF 477, Revision 3 GO2-13-043, Request for Technical Specification Interpretation Regarding the Offsite Power Supplies to the Onsite Class 1E AC Power Distribution System2013-03-13013 March 2013 Request for Technical Specification Interpretation Regarding the Offsite Power Supplies to the Onsite Class 1E AC Power Distribution System ML12011A1492011-12-14014 December 2011 Columbia, Technical Specification (TS) Basis, Rev. 69, Licensee Controlled Specifications (LCS) Rev. 67 and Operational Quality Assurance Program Description (Oqapd), Rev. 44 ML1013903692010-05-11011 May 2010 Columbia Generating Station, License Amendment Request to Change Technical Specifications in Support of Prnm/Arts/Mella Implementation GO2-09-011, License Amendment Request to Revise Control Rod Notch Testing Frequency Using the Consolidated Line Item Improvement Process (CLIIP) for TSTF-4752009-01-14014 January 2009 License Amendment Request to Revise Control Rod Notch Testing Frequency Using the Consolidated Line Item Improvement Process (CLIIP) for TSTF-475 ML0826100562008-09-30030 September 2008 Tech Spec Pages for Amendment No. 210 Revised TS 3.3.5.2 RCIC System Instrumentation, and TS 3.5.2 ECCS-Shotdown to Increase Storage Tank Level GO2-08-124, License Amendment Request for Proposed Changes to Columbia Technical Specification 3.3.3.1; Change Group 1 Primary Containment Isolation Valves Reactor Water Level Isolation Signal from Level 2 to Level 12008-09-0909 September 2008 License Amendment Request for Proposed Changes to Columbia Technical Specification 3.3.3.1; Change Group 1 Primary Containment Isolation Valves Reactor Water Level Isolation Signal from Level 2 to Level 1 ML0822506802008-07-16016 July 2008 Columbia - License Amendment Request for Changes to Technical Specifications Involving Core Operating Limits Report and Scram Time Testing GO2-08-071, License Amendment Request for Adoption of TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities2008-05-0707 May 2008 License Amendment Request for Adoption of TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities GO2-07-123, License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level2007-08-0808 August 2007 License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level GO2-07-116, Request for Amendment to Technical Specification to Modify Requirements Regarding Control Room Envelope Habitability Using the Consolidated Line Item Improvement Process (CLIIP)2007-07-30030 July 2007 Request for Amendment to Technical Specification to Modify Requirements Regarding Control Room Envelope Habitability Using the Consolidated Line Item Improvement Process (CLIIP) GO2-07-112, License Amendment Request for Proposed Changes to Technical Specifications: Miscellaneous Administrative Changes Including Adoption of Approved TSTF Travelers 284, 479, and 4852007-07-30030 July 2007 License Amendment Request for Proposed Changes to Technical Specifications: Miscellaneous Administrative Changes Including Adoption of Approved TSTF Travelers 284, 479, and 485 GO2-07-111, License Amendment Request for Proposed Changes to Columbia Technical Specifications: Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves2007-07-30030 July 2007 License Amendment Request for Proposed Changes to Columbia Technical Specifications: Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves GO2-07-109, License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level2007-07-26026 July 2007 License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level ML0709204712007-05-0101 May 2007 Technical Specification Pages - Issuance of Amendment No. 204 AC and DC Electrical Power ML0706400652007-03-23023 March 2007 Technical Specification, AC Sources - Operating 3.8.1 GO2-07-024, GO2-07-024 - Columbia Generating Station - Exigent License Amendment Request - Amend Operating License to Revise TS 3.6.1.7 Suppression Chamber-to-Drywell Vacuum Breakers2007-02-0202 February 2007 GO2-07-024 - Columbia Generating Station - Exigent License Amendment Request - Amend Operating License to Revise TS 3.6.1.7 Suppression Chamber-to-Drywell Vacuum Breakers GO2-06-061, Request for Amendment to Technical Specifications Surveillance Requirements for the Suppression Chamber-to-Drywell Vacuum Breakers and the Drywell-to-Suppression Chamber Bypass Leakage Test2006-04-18018 April 2006 Request for Amendment to Technical Specifications Surveillance Requirements for the Suppression Chamber-to-Drywell Vacuum Breakers and the Drywell-to-Suppression Chamber Bypass Leakage Test GO2-06-042, Revised Technical Specification Bases Change (for Information) and Summary of Commitments Associated with the License Amendment Requests for Extension of Diesel Generator Completion Time2006-03-20020 March 2006 Revised Technical Specification Bases Change (for Information) and Summary of Commitments Associated with the License Amendment Requests for Extension of Diesel Generator Completion Time GO2-05-184, Supplement to the License Amendment Request for a One-Time Extension to Technical Specification 3.7.12005-11-15015 November 2005 Supplement to the License Amendment Request for a One-Time Extension to Technical Specification 3.7.1 ML0507000912005-03-0909 March 2005 Technical Specification Pages (Amd. 190) Re Elimination of Requirements to Provide Monthly Operating Reports & Annual Occupational Radiation Exposure Reports GO2-04-137, Request for Amendment to Technical Specifications for One-Time Extension of Containment Leak Rate Test Interval2004-08-0505 August 2004 Request for Amendment to Technical Specifications for One-Time Extension of Containment Leak Rate Test Interval ML0415405452004-05-19019 May 2004 Application for Amendment of Facility Operating for Extension of Diesel Generator Completion Time GO2-02-192, Request for Amendment to TS 4.2.1 and 5.6.5.b, Corrections to Original Submittal2002-11-27027 November 2002 Request for Amendment to TS 4.2.1 and 5.6.5.b, Corrections to Original Submittal 2023-05-01
[Table view] Category:Amendment
MONTHYEARGO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications GO2-23-035, Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-03-0909 March 2023 Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling GO2-22-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process2022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process GO2-20-004, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR2020-01-27027 January 2020 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR GO2-19-098, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2019-09-12012 September 2019 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules GO2-19-119, Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating2019-08-15015 August 2019 Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating GO2-17-181, License Amendment Request to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-12-12012 December 2017 License Amendment Request to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements GO2-17-194, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-11-15015 November 2017 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control GO2-17-022, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-522 Revision 02017-01-19019 January 2017 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-522 Revision 0 GO2-16-119, License Amendment Request for One-Time 7 Day Extension of Completion Time for TS Condition 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A2016-11-0808 November 2016 License Amendment Request for One-Time 7 Day Extension of Completion Time for TS Condition 3.5.1.A, 3.6.1.5.A, and 3.6.2.3.A GO2-15-108, Provides Affected Technical Specification Pages Supporting License Amendment Request for Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-423, Revision 1, Using the Consolidated Line Item Improvement Process2015-08-11011 August 2015 Provides Affected Technical Specification Pages Supporting License Amendment Request for Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-423, Revision 1, Using the Consolidated Line Item Improvement Process GO2-15-075, Exigent License Amendment Request - Extension of Implementation Period for Amendment 232 Changing Technical Specification Table 3.3.1.1-1 Function 7 Scram Discharge Volume Water Level-High.2015-05-15015 May 2015 Exigent License Amendment Request - Extension of Implementation Period for Amendment 232 Changing Technical Specification Table 3.3.1.1-1 Function 7 Scram Discharge Volume Water Level-High. ML14010A0302014-02-11011 February 2014 Issuance of Amendment No. 227, Request to Adopt Technical Specification Task Force (TSTF)-477, Revision 3, Adding an Action Statement for Two Inoperable Control Room Air Conditioning Subsystem ML13247A6592013-07-25025 July 2013 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF 477, Revision 3 GO2-09-011, License Amendment Request to Revise Control Rod Notch Testing Frequency Using the Consolidated Line Item Improvement Process (CLIIP) for TSTF-4752009-01-14014 January 2009 License Amendment Request to Revise Control Rod Notch Testing Frequency Using the Consolidated Line Item Improvement Process (CLIIP) for TSTF-475 ML0826100562008-09-30030 September 2008 Tech Spec Pages for Amendment No. 210 Revised TS 3.3.5.2 RCIC System Instrumentation, and TS 3.5.2 ECCS-Shotdown to Increase Storage Tank Level GO2-08-124, License Amendment Request for Proposed Changes to Columbia Technical Specification 3.3.3.1; Change Group 1 Primary Containment Isolation Valves Reactor Water Level Isolation Signal from Level 2 to Level 12008-09-0909 September 2008 License Amendment Request for Proposed Changes to Columbia Technical Specification 3.3.3.1; Change Group 1 Primary Containment Isolation Valves Reactor Water Level Isolation Signal from Level 2 to Level 1 ML0822506802008-07-16016 July 2008 Columbia - License Amendment Request for Changes to Technical Specifications Involving Core Operating Limits Report and Scram Time Testing GO2-08-071, License Amendment Request for Adoption of TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities2008-05-0707 May 2008 License Amendment Request for Adoption of TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities GO2-07-123, License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level2007-08-0808 August 2007 License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level GO2-07-111, License Amendment Request for Proposed Changes to Columbia Technical Specifications: Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves2007-07-30030 July 2007 License Amendment Request for Proposed Changes to Columbia Technical Specifications: Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves GO2-07-116, Request for Amendment to Technical Specification to Modify Requirements Regarding Control Room Envelope Habitability Using the Consolidated Line Item Improvement Process (CLIIP)2007-07-30030 July 2007 Request for Amendment to Technical Specification to Modify Requirements Regarding Control Room Envelope Habitability Using the Consolidated Line Item Improvement Process (CLIIP) GO2-07-109, License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level2007-07-26026 July 2007 License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level ML0709204712007-05-0101 May 2007 Technical Specification Pages - Issuance of Amendment No. 204 AC and DC Electrical Power ML0706400652007-03-23023 March 2007 Technical Specification, AC Sources - Operating 3.8.1 GO2-06-061, Request for Amendment to Technical Specifications Surveillance Requirements for the Suppression Chamber-to-Drywell Vacuum Breakers and the Drywell-to-Suppression Chamber Bypass Leakage Test2006-04-18018 April 2006 Request for Amendment to Technical Specifications Surveillance Requirements for the Suppression Chamber-to-Drywell Vacuum Breakers and the Drywell-to-Suppression Chamber Bypass Leakage Test GO2-05-184, Supplement to the License Amendment Request for a One-Time Extension to Technical Specification 3.7.12005-11-15015 November 2005 Supplement to the License Amendment Request for a One-Time Extension to Technical Specification 3.7.1 ML0507000912005-03-0909 March 2005 Technical Specification Pages (Amd. 190) Re Elimination of Requirements to Provide Monthly Operating Reports & Annual Occupational Radiation Exposure Reports GO2-04-137, Request for Amendment to Technical Specifications for One-Time Extension of Containment Leak Rate Test Interval2004-08-0505 August 2004 Request for Amendment to Technical Specifications for One-Time Extension of Containment Leak Rate Test Interval ML0415405452004-05-19019 May 2004 Application for Amendment of Facility Operating for Extension of Diesel Generator Completion Time GO2-02-192, Request for Amendment to TS 4.2.1 and 5.6.5.b, Corrections to Original Submittal2002-11-27027 November 2002 Request for Amendment to TS 4.2.1 and 5.6.5.b, Corrections to Original Submittal GO2-02-111, Amendment Request to Revise Minimum Emergency Diesel Generator Output Voltage Specified in Technical Specification Limiting Condition for Operation 3.8.12002-07-16016 July 2002 Amendment Request to Revise Minimum Emergency Diesel Generator Output Voltage Specified in Technical Specification Limiting Condition for Operation 3.8.1 2023-05-01
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Sudesh K. Gambhir EN~ERGY Technical Services P.O. Box 968, Mail Drop PE04 Richland, WA 99352-0968 Ph. 509-377-8313 F. 509-377-2354 sgambhir@energy-northwest.com July 26, 2007 G02-07-109 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 LICENSE AMENDMENT REQUEST TO TECHNICAL SPECIFICATIONS ASSOCIATED WITH CONDENSATE STORAGE TANK LEVEL
Dear Sir or Madam:
Pursuant to 10 CFR 50.90, Energy Northwest hereby requests an amendment to the Technical Specifications (TS) for Columbia Generating Station (Columbia)
Operating License (NPF-21).
The proposed change would revise the requirements of TS LCO 3.3.5.2, Reactor Core Isolation Cooling (RCIC) System Instrumentation and TS LCO 3.5.2, ECCS -Shutdown.
It is requested that these sections be modified to reflect an increase in the allowable value for Condensate Storage Tank level-low function in Table 3.3.5.2-1 and an increase in the required Condensate Storage Tank level of SR 3.5.2.2.These changes reflect corrections that were made to supporting calculations for these two values.The proposed changes have been evaluated in accordance with 10 CFR 50.91 using criteria in 10 CFR 50.92(c) and this change presents a no significant hazards consideration.
The basis for this determination is provided in Attachment 1 to this letter.The proposed change does not involve any new commitments.
Energy Northwest requests approval of these changes prior to August 1, 2008. Once approved, the amendment will be implemented within 60 days. This implementation period will provide adequate time for station documents to be revised using the appropriate change control mechanisms.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b), Energy Northwest is notifying the State of Washington of this application for change to the TS by transmitting a copy of this letter and its attachments to the designated State Official.
LICENSE AMENDMENT REQUEST TO TECHNICAL SPECIFICATIONS ASSOCIATED WITH CONDENSATE STORAGE TANK LEVEL Page 2 If you have any questions or require additional information, please contact GV Cullen, Licensing Supervisor at (509) 377-6105.I declare under penalty of perjury that the foregoing is true and correct. Executed on the date of this letter.Respectfully, S mbhir Vice President, Technical Services Attachments:
- 1. Evaluation of the Proposed Change 2. Proposed Technical Specification Changes (mark-up)3. Proposed Technical Specification Pages (re-typed)
- 4. Changes to Technical Specification Bases (reference only)cc: BS Mallett -NRC RIV CF Lyon -NRC NRR NRC Senior Resident Inspector/988C RN Sherman -BPA/1 399 WA Horin -Winston & Strawn JO Luce -EFSEC RR Cowley -WDOH LICENSE AMENDMENT REQUEST TO TECHNICAL SPECIFICATIONS ASSOCIATED WITH CONDENSATE STORAGE TANK LEVEL Attachment 1 Page 1 of 5 Licensee Evaluation
1.0 DESCRIPTION
This letter is a request to amend the Operating License (NPF-21) for Columbia Generating Station (Columbia).
The proposed change would revise the requirements of TS LCO 3.3.5.2, Reactor Core Isolation Cooling (RCIC) System Instrumentation and TS LCO 3.5.2, ECCS -Shutdown.It is requested that these sections be modified to reflect an increase in the allowable value for Condensate Storage Tank level-low function in Table 3.3.5.2-1 and an increase in the required Condensate Storage Tank level of SR 3.5.2.2. These changes reflect corrections that were made to supporting calculations for these two values.
2.0 PROPOSED CHANGE
Energy Northwest (EN) proposes the following two changes to the Columbia Technical Specifications (TSs): 1. Revise the allowable value for Condensate Storage Tank Level -Low in Table 3.3.5.2-1, Reactor Core Isolation Cooling System Instrumentation, from "> 446 ft 0 inches elevation" to "> 447 ft 7 inches elevation" 2. Revise the required Condensate Storage Tank (CST) water level in SR 3.5.2.2 from "> 14.8 ft in a single CST or > 9.1 ft in each CST" to "> 16.5 ft in a single CST or > 10.5 ft in each CST"
3.0 BACKGROUND
Both of the proposed changes were identified during the process of developing a formal design basis record for the Reactor Core Isolation Cooling (RCIC) system. These proposed changes represent corrections related to calculational errors that were identified in the process of documenting the design basis.Change to TS Table 3.3.5.2-1 TS Table 3.3.5.2-1 provides a list RCIC system functions for which instrumentation is required to be provided.
The instruments required to meet function three, "Condensate Storage Tank Level-Low" are RCIC-LS-15A and 15B. These instruments initiate an automatic transfer of RCIC pump suction from the CST to the suppression pool on low CST level. They are required to be set high enough to ensure adequate pump suction head while water is being taken from the CST. The value for automatic transfer is set high enough to ensure that during swap-over of suction from the CST to the suppression pool, the volume in the CST will remain above the required submergence level to prevent vortexing.
T he current TS allowable value is >446' 0".
LICENSE AMENDMENT REQUEST TO TECHNICAL SPECIFICATIONS ASSOCIATED WITH CONDENSATE STORAGE TANK LEVEL Attachment 1 Page 2 of 5 It was discovered that the plant specific calculation (E/I-02-93-1272) used to support the existing values for the CST level setpoint incorrectly based the vortex limit on the centerline of the suction pipe (445' 4") feeding the RCIC pump when it should have been based on the upper edge of the pipe (446' 3.625"). The new lower analytical limit was subsequently determined to be 447' 1". Accounting for drift and loop uncertainties at approximately 1", the new calculated minimum setting would need to be 447' 2". To provide additional conservatism, EN proposes to add another 5" for a TS allowable of>447' 7". Currently, the level switch setting for both level switches are set conservatively at 448' 3" in compliance with Licensee Controlled Specifications (LCS) Table 1.3.5.3-1.
Change to SR 3.5.2.2 This surveillance requires that for operability of the High Pressure Core Spray (HPCS)System, either the suppression pool or the CSTs provide adequate volume (135,000 gallons) to minimize the consequences of a drain down event while in Mode 4 or Mode 5 (if required).
There are two Condensate Storage Tanks, each with a nominal capacity of 400,000 gallons. For the CSTs to satisfy this surveillance requirement there must either be two tanks each with 67,500 gallons available or else one tank with 135,000 gallons available.
While in standby, the HPCS pump is normally aligned to the CSTs to minimize the injection of suppression pool water into the Reactor Pressure Vessel (RPV). However, on low CST level or high suppression pool level an automatic transfer of the HPCS pump suction to the suppression pool occurs upon activation of the level switches.
Of particular concern are the measurement effects on the CST low level switches (HPCS-LS-1A and 1B). When the level in the CSTs fall below a preset level, contact closure from HPCS-LS-1A and 1B, with one out of two logic, signals the HPCS suction valve from the suppression pool to open. Opening of the suppression pool suction valve signals the CST suction valve to close.It was discovered that the calculated minimum level to assure 135,000 gallons in the CSTs in plant specific calculation (E/1-02-91-1011) did not take into consideration the plant conditions at which automatic transfer from the CST to the suppression pool could take place. These level switches are not connected directly to the CSTs but rather on a standpipe located downstream on the suction line in the reactor building.
Thus, they are influenced by such factors as differential head between the tank and the standpipe (due primarily to flow losses), reactor building temperature, and reactor building pressure.Previously, the calculation did not address the head loss that occurs in the switches when the HPCS pump is drawing water from the CST. When taking into consideration the effects of full HPCS flow on the sensing instrument, it was discovered that premature switching could occur due to a sensed lower level by HPCS-LS-1A and 1 B than that which actually exists in the tanks. After takihg into consideration the effect that flow had on the level sensors, it was determined that an additional margin of 1.4 ft in two tanks and 1.7 ft in one tank was necessary to assure 135,000 gallons was available to inject into the Reactor Pressure Vessel (RPV).
LICENSE AMENDMENT REQUEST TO TECHNICAL SPECIFICATIONS ASSOCIATED WITH CONDENSATE STORAGE TANK LEVEL Attachment 1 Page 3 of 5 As a compensatory measure, the surveillance procedures that are used to satisfy SR 3.5.2.2 for CST level have been revised to reflect this concern.4.0 TECHNICAL ANALYSIS In each case, the proposed change reflects a correction to previously calculated values used to support existing TS limits. Therefore, in order to restore the TS values to ensure that the underlying premise of LOOs 3.3.5.1 and 3.5.2.2 are met, this amendment request is necessary.
5.0 REGULATORY
ANALYSIS 5.1 No Significant Hazard Consideration EN 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 change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response:
No.The operation of Columbia in accordance with the proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated.
Neither of these changes affects the probability of any accident previously evaluated as they do not involve or impact accident initiators.
The proposed change to TS 3.3.5.1 would ensure that the consequences would remain the same as that previously evaluated for during any event in which the RCIC pump was utilized.
Adequate volume would be maintained in the CST whenever the RCIC pump was aligned to it to ensure that it did not experience loss of suction due to vortexing.
The proposed changes to TS 3.5.2.2 would ensure that the previously assumed volume of water in the CST would still be available to inject into the reactor vessel during Modes 4 and 5 should the suppression pool not meet minimum volume requirements.
Therefore, operation of Columbia in accordance with the proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response:
No.
LICENSE AMENDMENT REQUEST TO TECHNICAL SPECIFICATIONS ASSOCIATED WITH CONDENSATE STORAGE TANK LEVEL Attachment 1 Page 4 of 5 The operation of Columbia in accordance with the proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed change will not create a new or different kind of accident since it only affects the amount of water held in reserve to support reactor vessel inventory loss. The proposed change does not introduce any credible mechanisms for unacceptable radiation release nor does it require physical modification to the plant. The plant has operated well within the existing allowable values. The increased margin provided by the increased level will assure no new or different kinds of accidents result from the proposed change. Therefore, the operation of Columbia in accordance with the proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?Response:
No.The operation of Columbia in accordance with the proposed amendment will not involve a significant reduction in the margin of safety. The proposed amendment provides assurance that the RCIC pump suction will be transferred without loss of suction and that 135,000 gallons of CST inventory will continue to be available for injection into the RPV under worst case conditions.
Therefore, operation of Columbia in accordance with the proposed amendment will not involve a significant reduction in the margin of safety.5.2 Applicable Regulatory RequirementslCriteria The applicable regulatory criteria are found in 10 CFR 50, Appendix A, Criterion 13, and in 10 CFR 50 Appendix B, Criterion XII.10 CFR 50, Appendix A, Criterion 13-Instrumentation and control Instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems.Appropriate controls shall be provided to maintain these variables and systems within prescribed operating ranges.10 CFR 50, Appendix B, Criterion XlI-Control of Measuring and Test Equipment Measures shall be established to assure that tools, gages, instruments, and other measuring and testing devices used in activities affecting quality LICENSE AMENDMENT REQUEST TO TECHNICAL SPECIFICATIONS ASSOCIATED WITH CONDENSATE STORAGE TANK LEVEL Attachment 1 Page 5 of 5 are properly controlled, calibrated, and adjusted at specified periods to maintain accuracy within necessary limits.Revising the TSs to the ranges specified in this submittal will result in the prescribed CST operating ranges being maintained for normal operation, anticipated operational occurrences, and for accident conditions.
In addition, the establishment of the new ranges will provide the necessary limits for the instruments currently being used to satisfy the affected surveillance requirements.
6.0 ENVIRONMENTAL
CONSIDERATION EN has evaluated the proposed amendment against the criteria for identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.21. The proposed change meets the criteria for categorical exclusion as provided for in 10 CFR 51.22(c)(9).
The change request does not pose a significant hazards consideration nor does it involve an increase in the amounts, or a change in the types, of any effluent that may be released off-site.
Furthermore, this proposed request does not involve an increase in individual or cumulative occupational exposure.
7.0 REFERENCES
- 1. Calculation E/1-02-91-1011, "Calculation for Setting Range Determination for Instrument Loop" (HPCS-LS-IA and 1B)2. Calculation E/1-02-93-1272, "Calculation for Setting Range Determination for Instrument Loop RCIC Level Switch 15A & 15B" LICENSE AMENDMENT REQUEST TO TECHNICAL SPECIFICATIONS ASSOCIATED WITH CONDENSATE STORAGE TANK LEVEL Attachment 2 Proposed Technical Specifications Changes (mark-up)
RCIC System Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page I of 1)Reactor Core Isolation Cooling System Instrumentation CONDITIONS REQUIRED REFERENCED FROM CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION FUNCTION ACTION A.1 REQUIREMENTS VALUE 1. Reactor Vessel Water Level -Low Low, Level 2 2. Reactor Vessel Water Level -High, Level 8 3. Condensate Storage Tank Level -Low 4 B SR SR SR SR 2 C SR SR SR SR SR SR SR SR 3.3.5.2.1 3.3.5.2.2 3.3.5.2.3 3.3.5.2.4 3.3.5.2.1 3.3.5.2.2 3.3.5.2.3 3.3.5.2.4 3.3.5.2.1 3.3.5.2.2 3.3.5.2.3 3.3.5.2.4> -58 inches elevation D 4. Manual Initiation 2 C SR 3.3.5.2.4 NA Columbia Generating Station 3.3.5.2-4 Amendment No. +4-9 1691 ECCS- Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS
_SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each required low pressure ECCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> injection/spray subsystem, the suppression pool water level is _> 18 ft 6 inches.SR .3.5.2.2 Verify, for the required High Pressure Core 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Spray (HPCS) System, the: a. Suppression pool water level is> 18 ft 6 inches; or 16.5 b. Condensate storage tank (CST) water ,. level is > .t in a single CST orý ft in each CST.SR 3.5.2.3 Verify, for each required ECCS injection/
31 days spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.SR 3.5.2.4 --------------------
NOTE-----------------
One low pressure coolant injection (LPCI)subsystem may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned and not otherwise inoperable.
Verify each required ECCS injection/spray 31 days subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.(continued)
Columbia Generating Station 3.5.2-3 Amendment No.
1691 LICENSE AMENDMENT REQUEST TO TECHNICAL SPECIFICATIONS ASSOCIATED WITH CONDENSATE STORAGE TANK LEVEL Attachment 3 Proposed Technical Specification Pages (re-typed)
RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS
NOTES-------------------------------
- 1. Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC Function.2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 2 and 4; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 1 and 3 provided the associated Function maintains RCIC initiation capability.
SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.2.3 Perform CHANNEL CALIBRATION.
18 months SR 3.3.5.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months Columbia Generating Station 3.3.5.2-3 Amendment No. +44 1691 Table 3.3.5.2-1 (page 1 of 1)Reactor Core Isolation Cooling System Instrumentation CONDITIONS REQUIRED.....
REFERENCED
..CHANNELS FROM PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION FUNCTION ACTION A.1- REQUIREMENTS VALUE 1. Reactor Vessel Water 4 B SR 3.3.5.2.1
> -58 inches Level -Low Low. SR 3.3.5.2.2 Level 2 SR 3.3.5.2.3 SR 3.3.5.2.4 2. Reactor Vessel Water 2 C. -SR 3.3.5.2.1
< 56 inches Level -High. Level 8 SR 3.3.5.2.2 SR 3.3.5.2.3 SR 3.3.5.2.4 3. Condensate Storage 2 D SR 3.3.5.2.1
> 447 ft 7 Tank Level- Low SR 3.3.5.2.2 inches SR 3.3.5.2.3 elevation SR 3.3.5.2.4 4. Manual Initiation 2 C SR 3.3.5.2.4 NA I Columbia Generating Station 3.3.5.2-4 Amendment No. 149,169 ECCS -Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each required low pressure ECCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> injection/spray subsystem, the suppression pool water level is > 18 ft 6 inches.SR 3.5.2.2 Verify, for the required High Pressure Core 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Spray (HPCS) System, the: a. Suppression pool water level is> 18 ft 6 inches; or b. Condensate storage tank (CST) water l.evel is > 16.5 ft in a single CST or> 10.5 ft in each CST.SR 3.5.2.3 Verify, for each required ECCS injection/
31 days spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.SR 3.5.2.4 --------------------
NOTE------------------
One low pressure coolant injection (LPCI)subsystem may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned and not otherwise inoperable.
Verify each required ECCS injection/spray 31 days subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.(continued)
I Columbia Generating Station 3.5.2-3 Amendment No.149,15G, 165,169 ECCS- Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.5 Verify each required ECCS pump develops the In accordance specified flow rate with the specified with the developed head. Inservice Testing Program TOTAL DEVELOPED SYSTEM FLOW RATE HEAD LPCS >. 6350 gpm > 128 psid LPCI .7450 gpm > 26 psid HPCS 6350 gpm > 200 psid SR 3.5.2.6 -------------------
NOTE --------------------
Vessel injection/spray may be excluded.-------------------------------------------
Verify each required ECCS injection/spray 24 months subsystem actuates on an actual or simulated automatic initiation signal.Columbia Generating Station 3.5.2-4 Amendment No. 149,IS9 1691 LICENSE AMENDMENT REQUEST TO TECHNICAL SPECIFICATIONS ASSOCIATED WITH CONDENSATE STORAGE TANK LEVEL Attachment 4 Changes to Technical Specifications Bases (reference only)
ECCS- Shutdown B 3.5.2 BASES ACTIONS C.1, C.2, D.1, D.2. and D.3 (continued) stationing a dedicated 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 isolation is indicated).
This may be performed by an administrative check, by examining logs or other information, to determine if the components are out of service for maintenance or other reasons. It is not necessary to perform the Surveillances needed to demonstrate OPERABILITY of the components.
If, however, any required component is inoperable, then it must be restored to OPERABLE status. In this case, the Surveillances may need to be performed to restore the component to OPERABLE status.Actions must continue until all required components are OPERABLE.SURVEILLANCE REQUIREMENTS SR 3.5.2.1 and SR 3.5.2.2 The minimum water level of 18 ft 6 inches required for the suppression pool is periodically verified to ensure that the suppression pool will provide adequate net positive suction head (NPSH) for the ECCS pumps, recirculation volume (135,000 gallons consistent with the CST volume requirements described below), and vortex prevention.
With the suppression pool water level less than the required limit, all ECCS injection/spray subsystems are inoperable unless they are aligned to an OPERABLE CST (Ref. 5).When the suppression pool level is < 18 ft 6 inches, the HPCS System is considered OPERABLE only if it can take suction from the CST and the CST water level is sufficient to provide the required NPSH for the HPCS pump. Therefore, a verification that either the suppression pool water level is > 18 ft 6 inches or the HPCS System is aligned to take suction from the CST and the CST contains > 135,000 gallons of water. This volume of water is equivalent to a level of 14-rB$fft in a single CST or 9.-kft in each CST above the top of the suction line. This ens res that the HPCS System can supply makeup water to the RPV. Calculations that determine this water level are listed as References 3 and 4.Columbia Generating Station B 3.5.2-4 Revision 41