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Category:Letter type:CNS
MONTHYEARCNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing2018-07-19019 July 2018
License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing
CNS-18-032, Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report2018-07-12012 July 2018
Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report
CNS-18-031, Notice of Enforcement Discretion (NOED) Request2018-06-18018 June 2018
Notice of Enforcement Discretion (NOED) Request
CNS-18-028, 2017 Annual Radiological Environmental Operating Report2018-05-14014 May 2018
2017 Annual Radiological Environmental Operating Report
CNS-18-026, Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report2018-05-10010 May 2018
Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report
CNS-18-023, (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System2018-05-0808 May 2018
(Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System
CNS-18-025, Submittal of 2017 Annual Radioactive Effluent Release Report2018-04-30030 April 2018
Submittal of 2017 Annual Radioactive Effluent Release Report
CNS-18-022, Submittal of Emergency Plan Implementing Procedure2018-04-12012 April 2018
Submittal of Emergency Plan Implementing Procedure
CNS-18-017, Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-22018-03-24024 March 2018
Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-2
CNS-18-015, Commitment Change Evaluation Report for 20172018-03-22022 March 2018
Commitment Change Evaluation Report for 2017
CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-02-0808 February 2018
Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes
CNS-18-006, Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days2018-01-23023 January 2018
Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days
CNS-17-058, Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukus2017-12-28028 December 2017
Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushi
CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information2017-12-21021 December 2017
Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information
CNS-17-056, Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-22017-11-0101 November 2017
Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-2
CNS-17-056, Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-22017-10-23023 October 2017
Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-2
CNS-17-053, Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement2017-10-12012 October 2017
Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement
CNS-17-048, Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-1222017-09-29029 September 2017
Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-122
CNS-17-049, Submittal of Ufsar/Selected Licensee Commitment Changes Manual2017-09-28028 September 2017
Submittal of Ufsar/Selected Licensee Commitment Changes Manual
CNS-17-051, Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask2017-09-28028 September 2017
Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask
CNS-17-014, License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time2017-09-14014 September 2017
License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time
CNS-17-050, ISFSI - Registration of Spent Fuel Storage Cask2017-09-12012 September 2017
ISFSI - Registration of Spent Fuel Storage Cask
CNS-17-047, Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding2017-08-29029 August 2017
Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding
CNS-17-041, ISFSI - Registration of Spent Fuel Storage Cask2017-08-15015 August 2017
ISFSI - Registration of Spent Fuel Storage Cask
CNS-17-040, Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump2017-08-14014 August 2017
Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump
CNS-17-039, Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump2017-07-27027 July 2017
Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump
CNS-17-036, Mid-Cycle Power Uprate Ascension Startup Report2017-06-29029 June 2017
Mid-Cycle Power Uprate Ascension Startup Report
CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017
Technical Specification Bases Changes
CNS-17-029, Flood Hazard Mitigating Strategies Assessment Report Submittal2017-06-20020 June 2017
Flood Hazard Mitigating Strategies Assessment Report Submittal
CNS-17-030, Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core2017-06-20020 June 2017
Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core
CNS-17-024, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations2017-05-25025 May 2017
Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations
CNS-17-031, Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report2017-05-24024 May 2017
Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report
CNS-17-027, Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report2017-05-10010 May 2017
Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report
CNS-17-015, Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report2017-04-27027 April 2017
Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report
CNS-17-021, Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days2017-04-20020 April 2017
Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days
CNS-17-020, Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing2017-04-11011 April 2017
Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing
CNS-17-008, Commitment Change Evaluation Report for 20162017-03-16016 March 2017
Commitment Change Evaluation Report for 2016
CNS-17-004, Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.2017-01-26026 January 2017
Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.
CNS-17-002, End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report2017-01-0606 January 2017
End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report
CNS-16-080, Submittal of Emergency Plan Implementing Procedure2016-12-20020 December 2016
Submittal of Emergency Plan Implementing Procedure
CNS-16-077, Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-12-0808 December 2016
Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..2016-10-20020 October 2016
Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..
CNS-16-069, Submittal of Emergency Plan, Revision 16-22016-10-10010 October 2016
Submittal of Emergency Plan, Revision 16-2
CNS-16-068, Submittal of Emergency Plan Implementing Procedure Revisions2016-10-10010 October 2016
Submittal of Emergency Plan Implementing Procedure Revisions
CNS-16-064, License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 242016-09-0707 September 2016
License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 24
CNS-16-061, Submittal of Design Basis Specification for the Plant Fire Protection Revision 252016-08-12012 August 2016
Submittal of Design Basis Specification for the Plant Fire Protection Revision 25
CNS-16-051, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) an2016-08-0202 August 2016
License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) and
CNS-16-049, ISFSI Registration of Spent Fuel Storage Cask2016-07-14014 July 2016
ISFSI Registration of Spent Fuel Storage Cask
CNS-16-056, Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/00682016-07-13013 July 2016
Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/0068
CNS-16-050, Unit 2 - Ufsar/Selected Licensee Commitment Changes2016-07-12012 July 2016
Unit 2 - Ufsar/Selected Licensee Commitment Changes
2018-07-19
[Table view]
Category:Technical Specification
MONTHYEARRA-23-0042, Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change2023-04-24024 April 2023
Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change
RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023
Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023
License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies
ML22186A0082022-06-21021 June 2022
SLC Revision to 16.9-22, TS Bases 3.7.7
RA-22-0080, Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-0707 April 2022
Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System
RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022
Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition
RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022
Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
RA-21-0027, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-16016 September 2021
Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
RA-20-0207, Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation2020-12-0303 December 2020
Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation
RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019
License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description
RA-18-0219, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-12-0404 December 2018
Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes
RA-18-0226, Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System.2018-11-15015 November 2018
Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System.
CNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing2018-07-19019 July 2018
License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing
RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018
Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications
ML18130A8072018-05-10010 May 2018
Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications
RA-18-0001, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018
Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications
CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-02-0808 February 2018
Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes
RA-17-0005, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2017-11-0707 November 2017
Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing
RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017
Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.
CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017
Technical Specification Bases Changes
RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016
Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process
RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016
Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process
CNS-16-046, Technical Specification Bases Changes, B 3.7 Plant Systems2016-06-14014 June 2016
Technical Specification Bases Changes, B 3.7 Plant Systems
CNS-16-031, Technical Specification Bases Changes2016-04-26026 April 2016
Technical Specification Bases Changes
CNS-16-015, Technical Specification Bases Changes2016-02-18018 February 2016
Technical Specification Bases Changes
CNS-15-098, Technical Specification Bases Changes2015-12-14014 December 2015
Technical Specification Bases Changes
RA-15-0006, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 62015-06-24024 June 2015
Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 6
ML15175A4482015-06-24024 June 2015
Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6
ML15175A4472015-06-24024 June 2015
Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6
ML15175A4452015-06-24024 June 2015
Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6
ML15175A4422015-06-24024 June 2015
Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 3 of 6
MNS-15-022, Renewed Facility Operating License Nos. NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements2015-06-23023 June 2015
Renewed Facility Operating License Nos. NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements
CNS-15-054, Submittal of Technical Specification Bases Changes 5.5.142015-06-0202 June 2015
Submittal of Technical Specification Bases Changes 5.5.14
CNS-15-021, Technical Specification Bases Changes Made According to the Provisions of Technical Specification 5.5.14, Technical Specifications (TS) Bases Control Program.2015-03-0909 March 2015
Technical Specification Bases Changes Made According to the Provisions of Technical Specification 5.5.14, Technical Specifications (TS) Bases Control Program.
RA-14-0001, License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area2014-07-21021 July 2014
License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area
CNS-14-079, Technical Specification Bases Changes2014-06-18018 June 2014
Technical Specification Bases Changes
CNS-14-055, Technical Specification Bases Changes2014-05-0505 May 2014
Technical Specification Bases Changes
CNS-14-032, Request for Notice of Enforcement Discretion (NOED) Regarding Technical Specifications2014-03-10010 March 2014
Request for Notice of Enforcement Discretion (NOED) Regarding Technical Specifications
CNS-14-026, Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System.2014-02-17017 February 2014
Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System.
ML13269A0772013-09-23023 September 2013
Submittal of Technical Specification Bases Changes
ML13263A3732013-09-18018 September 2013
Technical Specification Bases Changes
ML13109A0802013-04-17017 April 2013
Technical Specification Bases Changes
ML12314A0152012-11-0606 November 2012
Technical Specification Bases Changes
ML12153A3282012-05-31031 May 2012
Proposed Technical Specifications Amendment TS 3.1.3, Moderator Temperature Coefficient (Mtc) TS 5.6.5, Core Operating Limits Report (COLR) License Amendment Request for Conditional Exemption of the End of Cycle (EOC) Mtc Measurement Method
ML11335A1482011-11-29029 November 2011
Technical Specification Bases Changes
ML11327A1492011-11-22022 November 2011
Proposed Technical Specifications (TS) and Bases Amendment TS and Bases 3.7.8, Nuclear Service Water System (Nsws)
ML11171A0422011-06-15015 June 2011
Changes to Technical Specification Bases Pursuant to 10CFR 50.4
ML11138A3042011-05-10010 May 2011
Technical Specification Bases Changes, Pursuant to 1OCFR 50.4
ML1108907012011-03-24024 March 2011
Duke Energy Carolinas - Technical Specification Bases Changes
ML1026500392010-09-16016 September 2010
License Amendment Request to Revise Technical Specification 5.3, Unit Staff Qualifications
2023-04-24
[Table view]
Category:Bases Change
MONTHYEARRA-23-0042, Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change2023-04-24024 April 2023
Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change
RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023
Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023
License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies
ML22186A0082022-06-21021 June 2022
SLC Revision to 16.9-22, TS Bases 3.7.7
RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022
Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition
RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022
Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
RA-18-0219, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-12-0404 December 2018
Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes
RA-18-0226, Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System.2018-11-15015 November 2018
Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System.
CNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing2018-07-19019 July 2018
License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing
CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-02-0808 February 2018
Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes
RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017
Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.
CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017
Technical Specification Bases Changes
RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016
Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process
RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016
Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process
CNS-16-046, Technical Specification Bases Changes, B 3.7 Plant Systems2016-06-14014 June 2016
Technical Specification Bases Changes, B 3.7 Plant Systems
CNS-16-031, Technical Specification Bases Changes2016-04-26026 April 2016
Technical Specification Bases Changes
CNS-16-015, Technical Specification Bases Changes2016-02-18018 February 2016
Technical Specification Bases Changes
CNS-15-098, Technical Specification Bases Changes2015-12-14014 December 2015
Technical Specification Bases Changes
ML15175A4452015-06-24024 June 2015
Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6
ML15175A4482015-06-24024 June 2015
Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6
ML15175A4472015-06-24024 June 2015
Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6
ML15175A4422015-06-24024 June 2015
Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 3 of 6
RA-15-0006, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 62015-06-24024 June 2015
Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 6
MNS-15-022, Renewed Facility Operating License Nos. NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements2015-06-23023 June 2015
Renewed Facility Operating License Nos. NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements
CNS-15-054, Submittal of Technical Specification Bases Changes 5.5.142015-06-0202 June 2015
Submittal of Technical Specification Bases Changes 5.5.14
CNS-15-021, Technical Specification Bases Changes Made According to the Provisions of Technical Specification 5.5.14, Technical Specifications (TS) Bases Control Program.2015-03-0909 March 2015
Technical Specification Bases Changes Made According to the Provisions of Technical Specification 5.5.14, Technical Specifications (TS) Bases Control Program.
RA-14-0001, License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area2014-07-21021 July 2014
License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area
CNS-14-079, Technical Specification Bases Changes2014-06-18018 June 2014
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CNS-14-055, Technical Specification Bases Changes2014-05-0505 May 2014
Technical Specification Bases Changes
CNS-14-032, Request for Notice of Enforcement Discretion (NOED) Regarding Technical Specifications2014-03-10010 March 2014
Request for Notice of Enforcement Discretion (NOED) Regarding Technical Specifications
CNS-14-026, Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System.2014-02-17017 February 2014
Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System.
ML13269A0772013-09-23023 September 2013
Submittal of Technical Specification Bases Changes
ML13263A3732013-09-18018 September 2013
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ML13109A0802013-04-17017 April 2013
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ML12314A0152012-11-0606 November 2012
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ML11335A1482011-11-29029 November 2011
Technical Specification Bases Changes
ML11327A1492011-11-22022 November 2011
Proposed Technical Specifications (TS) and Bases Amendment TS and Bases 3.7.8, Nuclear Service Water System (Nsws)
ML11171A0422011-06-15015 June 2011
Changes to Technical Specification Bases Pursuant to 10CFR 50.4
ML11138A3042011-05-10010 May 2011
Technical Specification Bases Changes, Pursuant to 1OCFR 50.4
ML1108907012011-03-24024 March 2011
Duke Energy Carolinas - Technical Specification Bases Changes
ML1019703652010-07-13013 July 2010
Submittal of Technical Specification Bases Changes
ML0935600772009-12-15015 December 2009
Technical Specifications Revision Request to Adopt TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to RCS Specific Activity.
ML0935005972009-12-14014 December 2009
Units 1 and 2 - License Amendment Request Applicable to Technical Specification 3.8.4, DC Sources-Operating
ML0908503412009-03-23023 March 2009
Technical Specification Bases Changes
ML0832605732008-11-12012 November 2008
Technical Specification Bases Changes
ML0828800982008-10-0808 October 2008
Proposed Technical Specifications and Bases Amendment, TS and Bases Administrative Changes
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ML0814300052008-05-15015 May 2008
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Transmittal of Technical Specification Bases Changes
2023-04-24
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Kelvin Henderson DUKE ENERGY. Vice President Catawba Nuclear Station Duke Energy CNOIVP 1 4800 Concord Road York, SC 29745 0: 803.701.4251 CNS-1 4-079 f: 803.701.3221 June 18, 2014 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Technical Specification Bases Changes Pursuant to 10CFR 50.4, please find attached changes to the Catawba Nuclear Station Technical Specification Bases. These Bases changes were made according to the provisions of Technical Specification 5.5.14, "Technical Specifications (TS) Bases Control Program."
Any questions regarding this information should be directed to Larry Rudy, Regulatory Affairs, at (803) 701-3084.
I certify that I am a duly authorized officer of Duke Energy Carolinas, LLC, and that the information contained herein accurately represents changes made to the Technical Specification Bases since the previous submittal.
Kelvin Henderson Vice President, Catawba Nuclear Station Attachment www.duke-energy.com
U.S. Nuclear Regulatory Commission June 18, 2014 Page 2 xc: V. M. McCree, Regional Administrator U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Mr. G.E. Miller NRC Project Manager (CNS)
U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop O-8G9A 11555 Rockville Pike Rockville, MD 20852-2746 G. A. Hutto, Senior Resident Inspector Catawba Nuclear Station
Catawba Nuclear Station eDUKE ENERGY, Duke Energy CNO1VP 1 4800 Concord Road York, SC 29745 June 18, 2014 Re: Catawba Nuclear Station Technical Specifications Bases Please replace the corresponding pages in your copy of the Catawba Technical Specifications Manual as follows:
REMOVE THESE PAGES INSERT THESE PAGES LIST OF EFFECTIVE PAGES Entire Bases Section (pages 13 - 19) Entire Bases Section (pages 13 - 19)
TAB 3.3.9 B 3.3.9-1 thru B 3.3.9-5 B 3.3.9-1 thru B 3.3.9-5 Revision 2 Revision 3 If you have any questions concerning the contents of this Technical Specification update, contact Kristi Byers at (803)701-3758.
Randy Hart Manager, Regulatory Compliance www.duke-energy.com
BASES Revision 1 4/08/99 ii Revision 2 3/01/05 iii Revision 1 6/21/04 B 2.1.1-1 Revision 0 9/30/98 B 2.1.1-2 Revision 1 12/19/03 B 2.1.1-3 Revision 1 12/19/03 B 2.1.2-1 Revision 0 9/30/98 B 2.1.2-2 Revision 0 9/30/98 B 2.1.2-3 Revision 0 9/30/98 B 3.0-1 Revision 1 3/19/07 B 3.0-2 Revision 1 3/19/07 B 3.0-3 Revision 2 3/19/07 B 3.0-4 Revision 3 3/19/07 B 3.0-5 Revision 3 3/19/07 B 3.0-6 Revision 2 3/19/07 B 3.0-7 Revision 2 3/19/07 B 3.0-8 Revision 3 3/19/07 B 3.0-9 Revision 2 3/19/07 B 3.0-10 Revision 3 3/19/07 B 3.0-11 Revision 3 3/19/07 B 3.0-12 Revision 3 3/19/07 B 3.0-13 Revision 3 3/19/07 B 3.0-14 Revision 3 3/19/07 B 3.0-15 Revision 1 3/19/07 B 3.0-16 Revision 1 3/19/07 B 3.0-17 Revision 0 3/19/07 B 3.0-18 Revision 0 3/19/07 B 3.0-19 Revision 0 3/19/07 B 3.1.1-1 thru Revision 3 5/05/11 B 3.1.1-6 Catawba Units 1 and 2 Page 13 6/02/14
B 3.1.2-1 thru Revision 2 5/05/11 B 3.1.2-5 B 3.1.3-1 Revision 4/26/00 B 3.1.3-2 Revision 4/26/00 B 3.1.3-3 Revision 4/26/00 B 3.1.3-4 Revision 4/26/00 B 3.1.3-5 Revision 4/26/00 B 3.1.3-6 Revision 4/26/00 B 3.1.4-1 thru Revision 5/05/11 B 3.1.4-9 B 3.1.5-1 thru Revision 2 5/05/11 B 3.1.5-4 B 3.1.6-1 thru Revision 1 5/05/11 B 3.1.6-6 B 3.1.7-1 Revision 0 9/30/98 B 3.1.7-2 Revision 2 1/08/04 B 3.1.7-3 Revision 2 1/08/04 B 3.1.7-4 Revision 2 1/08/04 B 3.1.7-5 Revision 2 1/08/04 B 3.1.7-6 Revision 2 1/08/04 B 3.1.8-1 thru Revision 2 5/05/11 B 3.1.8-6 B 3.2.1-1 thru Revision 4 5/05/11 B 3.2.1.-11 B 3.2.2-1 thru Revision 3 5/05/11 B 3.2.2-10 B 3.2.3-1 thru Revision 2 5/05/11 B 3.2.3-4 B 3.2.4-1 thru Revision 2 5/05/11 B 3.2.4-7 B 3.3.1-1 thru Revision 7 11/15/11 B.3.3.1-55 B 3.3.2-1 thru Revision 10 5/05/11 B 3.3.2-49 B 3.3.3-1 thru Revision 6 4/11/14 B.3.3.3-16 B 3.3.4-1 thru Revision 2 5/05/11 B 3.3.4-5 Catawba Units 1 and 2 Page 14 6/02/14
B 3.3.5-1 thru Revision 2 5/05/11 B 3.3.5-6 B 3.3.6-1 thru Revision 6 08/02/12 B 3.3.6-5 B 3.3.9-1 thru Revision 3 06/02/14 B 3.3.9-5 B 3.4.1-1 thru Revision 3 5/05/11 B 3.4.1-5 B 3.4.2-1 Revision 0 9/30/98 B 3.4.2-2 Revision 0 9/30/98 B 3.4.2-3 Revision 0 9/30/98 B 3.4.3-1 thru Revision 2 5/05/11 B 3.4.3-6 B 3.4.4-1 thru Revision 2 5/05/11 B 3.4.4-3 B 3.4.5-1 thru Revision 3 5/05/11 B 3.4.5-6 B 3.4.6-1 thru Revision 4 5/05/11 B 3.4.6-5 B 3.4.7-1 thru Revision 5 5/05/11 B 3.4.7-5 B 3.4.8-1 thru Revision 3 5/05/11 B 3.4.8-3 B 3.4.9-1 thru Revision 3 08/02/12 B 3.4.9-5 B 3.4.10-1 Revision 1 3/4/04 B 3.4.10-2 Revision 0 9/30/98 B 3.4.10-3 Revision 1 3/4/04 B 3.4.10-4 Revision 2 10/30/09 B 3.4.11-1 thru Revision 4 5/05/11 B 3.4.11-7 B 3.4.12-1 thru Revision 4 5/05/11 B 3.4.12-13 B 3.4.13-1 thru Revision 7 3/15/12 B 3.4.13-7 B 3.4.14-1 thru Revision 3 5/05/11 B 3.4.14-6 B 3.4.15-1 thru Revision 6 5/05/11 B 3.4.15-10 Catawba Units 1 and 2 Page 15 6/02/14
B 3.4.16-1 thru Revision 4 10/23/12 B 3.4.16-5 B 3.4.17-1 thru Revision 2 5/05/11 B 3.4.17-3 B 3.4.18-1 Revision 0 1/13/05 B 3.4.18-2 Revision 0 1/13/05 B 3.4.18-3 Revision 1 3/18/08 B 3.4.18-4 Revision 0 1/13/05 B 3.4.18-5 Revision 0 1/13/05 B 3.4.18-6 Revision 0 1/13/05 B 3.4.18-7 Revision 0 1/13/05 B 3.4.18-8 Revision 1 3/18/08 B 3.5.1-1 thru Revision 3 5/05/11 B 3.5.1-8 B 3.5.2-1 thru Revision 3 5/05/11 B 3.5.2-10 B 3.5.3-1 Revision 0 9/30/98 B 3.5.3-2 Revision 1 4/29/04 B 3.5.3-3 Revision 1 4/29/04 B 3.5.4-1 thru Revision 5 4/11/14 B.3.5.4-5 B 3.5.5-1 thru Revision 1 5/05/11 B 3.5.5-4 B 3.6.1-1 Revision 1 7/31/01 B 3.6.1-2 Revision 1 7/31/01 B 3.6.1-3 Revision 1 7/31/01 B 3.6.1-4 Revision 1 7/31/01 B 3.6.1-5 Revision 1 7/31/01 B 3.6.2-1 thru Revision 2 5/05/11 B 3.6.2-8 B 3.6.3-1 thru Revision 4 5/05/11 B 3.6.3-14 B 3.6.4-1 thru Revision 2 5/05/11 B 3.6.4-4 B 3.6.5-1 thru Revision 3 07/27/13 B 3.6.5-4 Catawba Units 1 and 2 Page 16 6/02/14
B 3.6.6-1 thru Revision 6 5/05/11 B 3.6.6-7 B 3.6.8-1 thru Revision 3 5/05/11 B 3.6.8-5 B 3.6.9-1 thru Revision 6 5/05/11 B 3.6.9-5 B 3.6.10-1 thru Revision 2 5/05/11 B 3.6.10-6 B 3.6.11-1 thru Revision 5 5/05/11 B 3.6.11-6 B 3.6.12-1 thru Revision 5 5/05/11 B 3.6.12-11 B 3.6.13-1 thru Revision 4 5/05/11 B 3.6.13-9 B 3.6.14-1 thru Revision 2 4/11/14 B 3.6.14-5 B 3.6.15-1 thru Revision 1 5/05/11 B 3.6.15-4 B 3.6.16-1 thru Revision 3 5/05/11 B 3.6.16-4 B 3.6.17-1 Revision 1 3/13/08 B 3.6.17-2 Revision 0 9/30/98 B 3.6.17-3 Revision 0 9/30/98 B 3.6.17-4 Revision 0 9/30/98 B 3.6.17-5 Revision 1 3/13/08 B 3.7.1-1 Revision 0 9/30/98 B 3.7.1-2 Revision 0 9/30/98 B 3.7.1-3 Revision 0 9/30/98 B 3.7.1-4 Revision 1 10/30/09 B 3.7.1-5 Revision 1 10/30/09 B 3.7.2-1 Revision 0 9/30/98 B 3.7.2-2 Revision 0 9/30/98 B 3.7.2-3 Revision 2 6/23/10 B 3.7.2-4 Revision 1 9/08/08 B 3.7.2-5 Revision 3 10/30/09 B 3.7.3-1 Revision 0 9/30/98 B 3.7.3-2 Revision 0 9/30/98 Catawba Units 1 and 2 Page 17 6/02/14
B 3.7.3-3 Revision 0 9/30/98 B 3.7.3-4 Revision 0 9/30/98 B 3.7.3-5 Revision 1 9/08/08 B 3.7.3-6 Revision 2 10/30/09 B 3.7.4-1 thru Revision 2 5/05/11 B 3.7.4-4 B 3.7.5-1 thru Revision 3 5/05/11 B 3.7.5-9 B 3.7.6-1 thru Revision 4 08/02/12 B 3.7.6-3 B 3.7.7-1 thru Revision 2 5/05/11 B 3.7.7-5 B 3.7.8-1 thru Revision 5 08/09/13 B 3.7.8-8 B 3.7.9-1 thru Revision 3 5/05/11 B 3.7.9-4 B 3.7.10-1 thru Revision 10 10/24/11 B 3.7.10-9 B 3.7.11-1 thru Revision 3 10/24/11 B 3.7.11-4 B 3.7.12-1 thru Revision 6 1/09/13 B 3.7.12-7 B 3.7.13-1 thru Revision 4 5/05/11 B 3.7.13-5 B 3.7.14-1 thru Revision 2 5/05/11 B 3.7.14-3 B 3.7.15-1 thru Revision 2 5/05/11 B 3.7.15-4 B 3.7.16-1 Revision 2 9/27/06 B 3.7.16-2 Revision 2 9/27/06 B 3.7.16-3 Revision 2 9/27/06 B 3.7.16-4 Revision 0 9/27/06 B 3.7.17-1 thru Revision 2 5/05/11 B 3.7.17-3 B 3.8.1-1 thru Revision 5 07/27/13 B.3.8.1-29 B 3.8.2-1 Revision 0 9/30/98 B 3.8.2-2 Revision 0 9/30/98 Catawba Units 1 and 2 Page 18 6/02/14
B 3.8.2-3 Revision 0 9/30/98 B 3.8.2-4 Revision 1 5/10/05 B 3.8.2-5 Revision 2 5/10/05 B 3.8.2-6 Revision 1 5/10/05 B 3.8.3-1 thru Revision 4 5/05/11 B 3.8.3-8 B 3.8.4-1 thru Revision 10 5/05/11 B3.8.4.1 0 B 3.8.5-1 Revision 0 9/30/98 B 3.8.5-2 Revision 2 7/29/03 B 3.8.5-3 Revision 1 7/29/03 B 3.8.6-1 thru Revision 4 5/05/11 B 3.8.6-7 B 3.8.7-1 thru Revision 3 5/05/11 B 3.8.7-4 B 3.8.8-1 thru Revision 3 5/05/11 B 3.8.8-4 B 3.8.9-1 thru Revision 2 5/05/11 B 3.8.9-10 B 3.8.10-1 thru Revision 3 5/05/11 B 3.8.10-4 B 3.9.1-1 thru Revision 3 5/05/11 B 3.9.1-4 B 3.9.2-1 thru Revision 4 5/05/11 B 3.9.2.4 B 3.9.3-1 thru Revision 4 5/05/11 B 3.9.3-5 B 3.9.4-1 thru Revision 4 5/05/11 B 3.9.4-4 B 3.9.5-1 thru Revision 3 5/05/11 B 3.9.5-4 B 3.9.6-1 thru Revision 2 5/05/11 B 3.9.6-3 B 3.9.7-1 thru Revision 1 5/05/11 B 3.9.7-3 Catawba Units 1 and 2 Page 19 6/02/14
BDMS B 3.3.9 B 3.3 INSTRUMENTATION B 3.3.9 Boron Dilution Mitigation System (BDMS)
BASES BACKGROUND The primary purpose of the BDMS is to mitigate the consequences of the inadvertent addition of unborated primary grade water into the Reactor Coolant System (RCS) when the reactor is in a shutdown condition (i.e.,
MODES 3, 4, and 5).
The BDMS is described in the Bases for LCO 3.9.2, "BDMS".
APPLICABLE The BDMS senses abnormal increases in source range counts per SAFETY ANALYSES second (flux rate) and actuates CVCS and RWST valves to mitigate the consequences of an inadvertent boron dilution event as described in UFSAR, Chapter 15 (Ref. 1). The accident analyses rely on automatic BDMS actuation to mitigate the consequences of inadvertent boron dilution events.
The BDMS satisfies Criterion 3 of 10 CFR 50.36 (Ref. 2).
LCO LCO 3.3.9 provides the requirements for OPERABILITY of the instrumentation and controls that mitigate the consequences of a boron dilution event. Two redundant trains are required to be OPERABLE to provide protection against single failure.
The Shutdown Margin Monitor Alarm Ratio (set at < 2 times the steady state count rate) and signals to the various valves all must be OPERABLE for each train in the system to be considered OPERABLE.
APPLICABILITY The BDMS must be OPERABLE in MODES 3, 4, and 5 because the safety analysis identifies this system as the primary means to mitigate an inadvertent boron dilution of the RCS.
Catawba Units 1 and 2 B 3.3.9-1 Revision No. 3
BDMS B 3.3.9 BASES APPLICABILITY (continued)
The BDMS OPERABILITY requirements are not applicable in MODES I and 2 because an inadvertent boron dilution would be terminated by a source range trip, a trip on the Power Range Neutron Flux-High (low setpoint nominally 25% RTP), or Overtemperature AT. These RTS Functions are discussed in LCO 3.3.1, "RTS Instrumentation."
The requirements for OPERABILITY of the BDMS in MODE 6 are described in LCO 3.9.2, "Boron Dilution Mitigation System."
ACTIONS The most common cause of channel inoperability is outright failure or drift of the shutdown margin monitor sufficient to exceed the tolerance allowed by the unit specific calibration procedure. Typically, the drift is found to be small and results in a delay of actuation rather than a total loss of function. This determination of setpoint drift is generally made during the performance of a COT when the process instrumentation is set up for adjustment to bring it to within specification. If the Trip Setpoint is less conservative than the tolerance specified by the calibration procedure, the channel must be declared inoperable immediately and the appropriate Condition entered.
A.1, A.2.1, A.2.2, A.3.1, and A.3.2 With one BDMS train inoperable, redundancy for mitigation of dilution events is no longer available. In this case, the BDMS train is required to be restored to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. As an alternative (Required Actions A.2.1 and A.2.2), operations involving positive reactivity additions must be suspended and valve NV-230 must be closed and secured within the following hour to isolate the unborated water sources. A third alternative (Required Actions A.3.1 and A.3.2) is to provide alternate methods of monitoring core reactivity conditions and controlling boron dilution incidents. Alternative monitoring may be provided by the two Source Range Neutron Flux monitors. These monitors must be verified to operate with an alarm ratio less than or equal to two times the steady state count rate (alarm R-value < 2.0). In addition, the combined flowrate from both reactor makeup water pumps must be verified within the next hour to be within the limits specified in the COLR. Required Action A.2.1 is modified by a Note, which permits plant temperature changes provided the temperature change is accounted for in the calculated SDM and that keff remains < 0.99. Introduction of temperature changes, including temperature increases when a positive MTC exists, must be evaluated to ensure they do not result in a loss of required SDM or adequate margin to criticality.
Catawba Units 1 and 2 B 3.3.9-2 Revision No. 3
BDMS B 3.3.9 BASES ACTIONS (continued)
The Completion Times are based on the remaining OPERABLE BDMS train and the low probability of an event occurring during this time.
B.1, B.2.1, B.2.2. B.3.1. and B.3.2 With both BDMS trains inoperable, the automatic capability for mitigation of dilution events is no longer available. In this case, one BDMS train is required to be restored to OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. As an alternative (Required Actions B.2.1 and B.2.2), operations involving positive reactivity additions must be suspended and valve NV-230 must be closed and secured within the following hour to isolate the unborated water sources. A third alternative (Required Actions B.3.1 and B.3.2) is to provide alternate methods of monitoring core reactivity conditions and controlling boron dilution incidents. Alternative monitoring may be provided by the two Source Range Neutron Flux monitors. These monitors must be verified to operate with an alarm ratio less than or equal to two times the steady state count rate (alarm R-value < 2.0). In addition, the combined flowrate from both reactor makeup water pumps must be verified within the next hour to be within the limits specified in the COLR. Required Action B.2.1 is modified by a Note, which permits plant temperature changes provided the temperature change is accounted for in the calculated SDM and that keff remains < 0.99. Introduction of temperature changes, including temperature increases when a positive MTC exists, must be evaluated to ensure they do not result in a loss of required SDM or adequate margin to criticality.
The Completion Times are based on the low probability of an event occurring during this time.
SURVEILLANCE SR 3.3.9.1 REQUIREMENTS SR 3.3.9.1 is the performance of a CHANNEL CHECK on the BDMS, which is a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that the two indication channels should be consistent with core conditions.
Changes in fuel loading and core geometry can result in significant differences, but each channel should be consistent with its local conditions. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.
Catawba Units 1 and 2 B 3.3.9-3 Revision No. 3
BDMS B 3.3.9 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.3.9.2 SR 3.3.9.2 is the performance of a COT for the BDMS, which is the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify the OPERABILITY of required alarm, interlock, display, and trip functions. The COT also includes adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpoints are within the required range and accuracy.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.
SR 3.3.9.3 SR 3.3.9.3 is performed on the BDMS to verify the actuation signal causes the appropriate valves to move to their correct position and the Reactor Makeup Water Pumps stop to mitigate a boron dilution accident.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.
SR 3.3.9.4 SR 3.3.9.4 is the performance of a CHANNEL CHECK on the Source Range Neutron Flux monitors, which is a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that the two indication channels should be consistent with core conditions. Changes in fuel loading and core geometry can result in significant differences, but each channel should be consistent with its local conditions.
A note is provided to clarify that the CHANNEL CHECK only needs to be performed on the Source Range Neutron Flux Monitors when used to satisfy Required Action A.3 or B.3.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.
Catawba Units 1 and 2 B 3.3.9-4 Revision No. 3
BDMS B 3.3.9 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.3.9.5 SR 3.3.9.5 verifies the combined flow rates from both Reactor Makeup Water Pumps are within the value specified in the COLR. This surveillance is only required when implementing Required Action A.3 or B.3. It ensures the assumptions in the analysis for the boron dilution event under these conditions are satisfied.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.
SR 3.3.9.6 SR 3.3.9.6 is the performance of a COT for the Source Range Neutron Flux monitors, which is the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify the OPERABILITY of required alarm, interlock, display, and trip functions.
The COT also includes adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpoints are within the required range and accuracy. These monitors must be verified to operate with an alarm ratio less than or equal to two times the steady state count rate (alarm R-value < 2.0). This SR is only required when the Source Range Neutron Flux Monitors are used to satisfy Required Action A.3 or B.3.
This surveillance must be performed prior to placing the monitors in service for Required Action A.3 or B.3 and at the specified Frequency thereafter. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.
REFERENCES 1. UFSAR, Chapter 15.
- 2. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).
- 3. Not used.
Catawba Units 1 and 2 B 3.3.9-5 Revision No. 3
