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Category:Letter
MONTHYEARIR 05000413/20240022024-08-0808 August 2024 Integrated Inspection Report 05000413-2024002 and 05000414-2024002 and Apparent Violation IR 05000269/20243012024-08-0808 August 2024 – Operator Licensing Examination Approval 05000269/2024301, 05000270/2024301, and 05000287/2024301 IR 05000269/20240102024-08-0101 August 2024 Focused Engineering Inspection - Age-Related Degradation Report 05000269/2024010 and 05000270/2024010 and 05000287/2024010 IR 05000413/20244032024-08-0101 August 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000413/2024403; 05000414/2024403 IR 05000369/20244042024-08-0101 August 2024 Cover Letter Security Baseline Inspection Report 05000369/2024404 and 05000370/2024404 IR 05000369/20253012024-07-29029 July 2024 Notification of Licensed Operator Initial Examination 05000369/2025301 and 05000370/2025301 IR 05000269/20240022024-07-25025 July 2024 Integrated Inspection Report 05000269/2024002 and 05000270/2024002 and 05000287/2024002 IR 05000369/20240022024-07-24024 July 2024 Integrated Inspection Report 05000369/2024002 and 05000370/2024002 ML24192A1312024-07-15015 July 2024 Licensed Operator Positive Fitness-For-Duty Test ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000369/20244012024-07-0303 July 2024 – Security Baseline Inspection Report 05000369/2024401 and 05000370/2024401 ML24183A2352024-06-29029 June 2024 Update 3 to Interim Report Regarding a Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 ML24178A0552024-06-26026 June 2024 Requalification Program Inspection – Catawba Nuclear Station ML24176A2802024-06-26026 June 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000369-2024404 and 05000370-2024404) IR 05000414/20240902024-06-24024 June 2024 NRC Inspection Report 05000414/2024090 and Preliminary White Finding and Apparent Violation ML24170A8632024-06-11011 June 2024 Flowserve June 11, 2024, Part 21 Notification - Redacted Version for Publishing IR 05000369/20240112024-06-0404 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000369/2024011 and 05000370/2024011 ML24144A1162024-05-28028 May 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000413/20240012024-05-10010 May 2024 Integrated Inspection Report 05000413/2024001 and 05000414/2024001 and Apparent Violation IR 05000369/20240012024-05-0808 May 2024 Integrated Inspection Report 05000369-2024001 and 05000370-2024001 and 07200038-2024001 IR 05000269/20240012024-05-0303 May 2024 Integrated Inspection Report 05000269/2024001, 05000270/2024001 and 05000287/2024001 ML24110A0382024-04-30030 April 2024 – Correction to Issuance of Amendment Nos. 330 and 309, Regarding Implementation of Technical Specifications Task Force (TSTF) Traveler TSTF 505, Revision 2, “Provide Risk-Informed Extended Completion Times - Ritstf IR 05000269/20244022024-04-24024 April 2024 Security Baseline Inspection Report 05000269/2024402 and 05000270/2024402 and 05000287/2024402 ML24108A0792024-04-16016 April 2024 EN 57079 Paragon Energy Solutions Email Forwarding Part 21 Interim Report Re Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 IR 05000369/20244032024-04-10010 April 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000369/2024403; and 05000370/2024403 ML24095A1072024-04-0808 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report (C1R27) IR 05000413/20230042024-02-0202 February 2024 Integrated Inspection Report 05000413-2023004 and 05000414-2023004 ML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application IR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) IR 05000369/20234022023-12-14014 December 2023 Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 IR 05000369/20240102023-10-13013 October 2023 Notification of McGuire Nuclear Station Comprehensive Engineering Team Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000369, 370/2024010 IR 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code 2024-08-08
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRA-23-0245, License Amendment Request Proposing to Revise Technical Specification 3.4.3, “Rcs Pressure and Temperature (P/T) Limits”2024-06-18018 June 2024 License Amendment Request Proposing to Revise Technical Specification 3.4.3, “Rcs Pressure and Temperature (P/T) Limits” RA-24-0136, Subsequent License Renewal Application Third Annual Update to the License Renewal Application and Subsequent License Renewal Application Supplement 52024-05-24024 May 2024 Subsequent License Renewal Application Third Annual Update to the License Renewal Application and Subsequent License Renewal Application Supplement 5 RA-23-0028, Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, “Add Action for More than One (D)Rpi Inoperable2024-05-23023 May 2024 Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, “Add Action for More than One (D)Rpi Inoperable ML24110A0382024-04-30030 April 2024 – Correction to Issuance of Amendment Nos. 330 and 309, Regarding Implementation of Technical Specifications Task Force (TSTF) Traveler TSTF 505, Revision 2, “Provide Risk-Informed Extended Completion Times - Ritstf RA-23-0182, Duke Energy Carolinas, LLC - License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program for a One-Time Extension of the Units 1, 2 and 3 Type a Leak Rate Test Frequency2023-11-16016 November 2023 Duke Energy Carolinas, LLC - License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program for a One-Time Extension of the Units 1, 2 and 3 Type a Leak Rate Test Frequency RA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023 Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power ML23188A0732023-07-0707 July 2023 Acceptance of Requested Licensing Action License Amendment Application to Revise Control Room Cooling Technical Specifications RA-18-0007, License Amendment Application to Revise Control Room Cooling Technical Specifications2023-06-19019 June 2023 License Amendment Application to Revise Control Room Cooling Technical Specifications RA-22-0292, License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-04-0404 April 2023 License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RA-18-0090, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-02-17017 February 2023 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors 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-18-0190, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-16016 February 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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 RA-22-0285, Subsequent License Renewal - Appendix E Environmental Report Supplement 22022-11-0707 November 2022 Subsequent License Renewal - Appendix E Environmental Report Supplement 2 RA-22-0157, Subsequent License Renewal Application First Annual Amendment to the License Renewal Application and Subsequent License Renewal Application Supplement 42022-06-0707 June 2022 Subsequent License Renewal Application First Annual Amendment to the License Renewal Application and Subsequent License Renewal Application Supplement 4 RA-22-0057, License Amendment Request to Address Technical Specifications Mode Change Limitations2022-03-31031 March 2022 License Amendment Request to Address Technical Specifications Mode Change Limitations 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-21-0320, License Amendment Request (LAR) to Revise the Applicability Term for Pressure and Temperature Limit Curves of Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits2021-12-20020 December 2021 License Amendment Request (LAR) to Revise the Applicability Term for Pressure and Temperature Limit Curves of Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits RA-21-0316, Subsequent License Renewal Application Supplement 32021-12-15015 December 2021 Subsequent License Renewal Application Supplement 3 RA-21-0197, William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility2021-12-14014 December 2021 William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility RA-21-0297, Subsequent License Renewal Application, Appendix E, Environmental Report Supplement 12021-11-11011 November 2021 Subsequent License Renewal Application, Appendix E, Environmental Report Supplement 1 RA-21-0288, Subsequent License Renewal Application Supplement 22021-11-11011 November 2021 Subsequent License Renewal Application Supplement 2 RA-21-0249, Subsequent License Renewal Application Supplement 12021-10-28028 October 2021 Subsequent License Renewal Application Supplement 1 RA-21-0005, Application to Revise Technical Specification 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required Inoperable LPSW Pump on a Temporary Basis2021-09-0202 September 2021 Application to Revise Technical Specification 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required Inoperable LPSW Pump on a Temporary Basis RA-19-0043, Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2021-06-0909 June 2021 Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RA-19-0039, License Amendment Request to Revise Technical Specifications to Adopt Two NRC-Approved Generic Technical Specification Changes2020-04-13013 April 2020 License Amendment Request to Revise Technical Specifications to Adopt Two NRC-Approved Generic Technical Specification Changes RA-19-0144, License Amendment Request for Measurement Uncertainty Recapture Power Uprate2020-02-19019 February 2020 License Amendment Request for Measurement Uncertainty Recapture Power Uprate RA-20-0011, Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2020-02-0606 February 2020 Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process RA-18-0156, Administrative License Amendment Request Proposing to Revise Technical Specification 3.0, Surveillance Requirement (SR) Applicability2019-09-0404 September 2019 Administrative License Amendment Request Proposing to Revise Technical Specification 3.0, Surveillance Requirement (SR) Applicability RA-19-0253, Proposed License Amendment Request to Revise the Oconee Nuclear Station Current Licensing Basis for High Energy Line Breaks Outside of the Containment Building2019-08-28028 August 2019 Proposed License Amendment Request to Revise the Oconee Nuclear Station Current Licensing Basis for High Energy Line Breaks Outside of the Containment Building 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-18-0036, License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits2019-07-0101 July 2019 License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits RA-18-0136, License Amendment Request Proposing a Revised Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, ...2018-11-0101 November 2018 License Amendment Request Proposing a Revised Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, ... RA-18-0198, (Cns), Units 1 & 2 - Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System2018-10-29029 October 2018 (Cns), Units 1 & 2 - Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System RA-18-0094, Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating2018-10-0808 October 2018 Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating RA-18-0026, Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Sections Associated with the Oconee Tornado Licensing Basis2018-09-14014 September 2018 Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Sections Associated with the Oconee Tornado Licensing Basis 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-18-0015, Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating.2018-07-10010 July 2018 Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating. RA-18-001, McGuire Nuclear Station, Units 1 and 2 - Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating.2018-07-10010 July 2018 McGuire Nuclear Station, Units 1 and 2 - Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating. MNS-18-001, Application to Revise Technical Specifications to Adopt TSTF-234-A Revision 1, Add Action for More than One Dpri Inoperable2018-05-31031 May 2018 Application to Revise Technical Specifications to Adopt TSTF-234-A Revision 1, Add Action for More than One Dpri Inoperable RA-18-0023, License Amendment Request (2017-05) to Add a Surveillance Requirement to Technical Specification 3.8.1, AC Sources2018-05-17017 May 2018 License Amendment Request (2017-05) to Add a Surveillance Requirement to Technical Specification 3.8.1, AC Sources 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 MNS-18-017, Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs2018-02-26026 February 2018 Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs MNS-17-026, Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated Missiles2017-12-0808 December 2017 Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated Missiles 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 ONS-2017-074, Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Section Associated with Tile Standby Shutdown Facility License Amendment Request No. 2017-032017-10-20020 October 2017 Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Section Associated with Tile Standby Shutdown Facility License Amendment Request No. 2017-03 MNS-17-031, License Amendment Request for Temporary Changes to Technical Specifications to Address an 'A' Train Nuclear Service Water System (Nsws) Non-Conforming Condition2017-09-14014 September 2017 License Amendment Request for Temporary Changes to Technical Specifications to Address an 'A' Train Nuclear Service Water System (Nsws) Non-Conforming Condition 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 2024-06-18
[Table view] Category:Technical Specification
MONTHYEARRA-24-0092, Application to Revise Technical Specification 3.7.7, “Low Pressure Service Water (LPSW) System,” to Extend the Completion Time for One Required LPSW Pump Inoperable on a One-Time Basis2024-07-29029 July 2024 Application to Revise Technical Specification 3.7.7, “Low Pressure Service Water (LPSW) System,” to Extend the Completion Time for One Required LPSW Pump Inoperable on a One-Time Basis RA-23-0028, Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, “Add Action for More than One (D)Rpi Inoperable2024-05-23023 May 2024 Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, “Add Action for More than One (D)Rpi Inoperable RA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023 Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power RA-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-22-0292, License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-04-0404 April 2023 License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RA-18-0190, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-16016 February 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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-21-0005, Application to Revise Technical Specification 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required Inoperable LPSW Pump on a Temporary Basis2021-09-0202 September 2021 Application to Revise Technical Specification 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required Inoperable LPSW Pump on a Temporary Basis 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 ML20237F4352020-09-0404 September 2020 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations RA-19-0039, License Amendment Request to Revise Technical Specifications to Adopt Two NRC-Approved Generic Technical Specification Changes2020-04-13013 April 2020 License Amendment Request to Revise Technical Specifications to Adopt Two NRC-Approved Generic Technical Specification Changes RA-20-0011, Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2020-02-0606 February 2020 Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process 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-18-0282, Technical Specification Bases Changes2019-06-26026 June 2019 Technical Specification Bases Changes RA-18-0281, Technical Specification Bases Changes2019-06-25025 June 2019 Technical Specification Bases Changes RA-18-0232, Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS2019-02-0505 February 2019 Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS 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. RA-18-0166, Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs2018-09-13013 September 2018 Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs 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 ML18191A5452018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages RA-18-001, Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages2018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages RA-18-0023, License Amendment Request (2017-05) to Add a Surveillance Requirement to Technical Specification 3.8.1, AC Sources2018-05-17017 May 2018 License Amendment Request (2017-05) to Add a Surveillance Requirement to Technical Specification 3.8.1, AC Sources 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 ONS-2018-013, Technical Specification Bases Changes2018-02-22022 February 2018 Technical Specification Bases Changes 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. ML17237A0462017-08-17017 August 2017 Document Transmittal Form Regarding Technical Specification Changes - Amendment Nos. 296/275 ML17237A0482017-08-17017 August 2017 Technical Specification Bases (Rev. 150) ML17237A0492017-08-17017 August 2017 Technical Specification Bases - List of Effected Sheets ONS-2017-050, Technical Specification Bases Change 2017-042017-07-21021 July 2017 Technical Specification Bases Change 2017-04 ONS-2017-052, Technical Specification Bases Change 2017-032017-07-20020 July 2017 Technical Specification Bases Change 2017-03 ONS-2017-043, Technical Specification Bases Change 2017-012017-07-20020 July 2017 Technical Specification Bases Change 2017-01 CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017 Technical Specification Bases Changes ML17186A0692017-06-26026 June 2017 Issue Tech Spec - List of Affected Pages ML17186A0682017-06-26026 June 2017 Tech Spec Bases - List of Affected Sections ML17186A0672017-06-26026 June 2017 Revision 151 to Tech Spec Bases - B 3.6.13 and B 3.6.14 ML17186A0662017-06-26026 June 2017 TS 3.6.13 Amendment 292/271 and TS 3.6.14 Amendment 294/273 ML17136A3602017-05-0303 May 2017 Technical Specification Amendment Nos. 285/264 ML17136A2792017-05-0303 May 2017 Technical Specification Leep, Rev. 109 ML17136A3612017-05-0303 May 2017 Technical Specification Bases, Revision 149 2024-07-29
[Table view] Category:Amendment
MONTHYEARRA-23-0028, Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, “Add Action for More than One (D)Rpi Inoperable2024-05-23023 May 2024 Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, “Add Action for More than One (D)Rpi Inoperable RA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023 Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power RA-22-0292, License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-04-0404 April 2023 License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RA-18-0190, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-16016 February 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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-22-0080, 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-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 ML20237F4352020-09-0404 September 2020 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations RA-20-0011, Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2020-02-0606 February 2020 Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process 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-18-000, 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 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 MNS-16-092, License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-12-19019 December 2016 License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML16305A1442016-10-20020 October 2016 Issue MNS Technical Specification 5.5 ML16133A4692016-05-0202 May 2016 Technical Specification 3.8.1, Amendments 282 and 261 ML16133A4462016-05-0202 May 2016 Technical Specification 3.7.7, Amendments 282 and 261 ML16133A4662016-05-0202 May 2016 Technical Specification 3.7.7 - Rev. 140, Amendments 282/261 ML16133A4442016-04-28028 April 2016 Technical Specification 3.7.5, Amendments 282 and 261 ML16133A4672016-04-28028 April 2016 Technical Specification 3.7.9, Amendments 282 and 261 ML16133A4422016-04-28028 April 2016 Technical Specification 3.5.2, Amendments 282 and 261 ML16133A4432016-04-28028 April 2016 Technical Specification 3.6.6, Amendments 282 and 261 ML16133A4452016-04-28028 April 2016 Technical Specification 3.7.6, Amendments 282 and 261 ML16133A4682016-04-28028 April 2016 Technical Specification 3.7.11, Amendment 282/261 MNS-15-069, Duke Energy Carolinas, LLC (Duke Energy), McGuire Nuclear Station, Unit 1 - License Amendment Request for One-Time Change to Technical Specification 3.5.2, Emergency Core Cooling Systems (ECCS) - Operating.2015-08-28028 August 2015 Duke Energy Carolinas, LLC (Duke Energy), McGuire Nuclear Station, Unit 1 - License Amendment Request for One-Time Change to Technical Specification 3.5.2, Emergency Core Cooling Systems (ECCS) - Operating. MNS-14-045, Responses to Request for Additional Information Related to License Amendment Request for One-Time Change to Technical Specification 3.8.4, DC Sources-Operating for Battery Replacement Dated October 28, 20132014-06-0303 June 2014 Responses to Request for Additional Information Related to License Amendment Request for One-Time Change to Technical Specification 3.8.4, DC Sources-Operating for Battery Replacement Dated October 28, 2013 ML13357A6742014-01-0808 January 2014 Issuance of Amendments Regarding the Temporary Technical Specification Change to Extend the Completion Time for an Inoperable Keowee Hydro Unit (TAC ME9021, ME9022, and ME9023) ML13304B4452013-10-28028 October 2013 Revised License Amendment Request for One-Time Change to Technical Specification 3.8.4, DC Sources-Operating for Battery Replacement ML12340A0682012-11-0707 November 2012 Technical Specifications & Tech Spec Bases Updates ML12307A3772012-10-30030 October 2012 (Ons), Units 1, 2, and 3, License Amendment Request to Clarify the Application of the 45-day Completion, Time of Technical Specification 3.8.1 Required Action C.2.2.5, License Amendment Request (LAR) No. 2012-14 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 ML11327A1492011-11-22022 November 2011 Proposed Technical Specifications (TS) and Bases Amendment TS and Bases 3.7.8, Nuclear Service Water System (Nsws) ML11311A1622011-10-31031 October 2011 Technical Specifications & Tech Spec Bases Updates ML1100500792010-12-28028 December 2010 Technical Specifications and Tech Spec Bases Manual Holders ML1026500392010-09-16016 September 2010 License Amendment Request to Revise Technical Specification 5.3, Unit Staff Qualifications ML1019002672010-06-29029 June 2010 License Amendment Request to Revise Reactor Trip System and Engineered Safety Feature Actuation System Technical Specifications ML0928600672009-09-30030 September 2009 Units 1 & 2 and Oconee, Units 1, 2, & 3 - License Amendment Request (LAR) Catawba and McGuire Containment Spray Nozzle and Oconee Reactor Building Spray and Cooling Systems Technical Specification Surveillance Requirement ML0925302402009-09-0303 September 2009 Request to Amend Technical Specification (TS) 3.7.10: Control Room Area Ventilation System ML0913800922009-05-11011 May 2009 Technical Specification Update ML0911202002009-02-27027 February 2009 Duke Energy Carolinas, LLC - License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0829005322008-10-0202 October 2008 Units 1 and 2 - Amendment to Technical Specification 3.6.13, Ice Condenser Doors, Revised Surveillance Requirements ML0823106722008-09-0808 September 2008 Issuance of Amendments Regarding (TAC MD6961 and MD6962) ML0825200142008-09-0202 September 2008 Request for Additional Information Associated with the License Amendment Request (LAR) for Low Pressure Service Water Reactor Building Waterhammer Prevention System Modification LAR No. 2006-05 ML0824900942008-09-0202 September 2008 Technical Specifications (TS) And/Or Bases Sections: 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation 3.3.3, Post Accident Monitoring (PAM) Instrumentation 3.5.4, Refueling Water Storage. ML0819807732008-07-30030 July 2008 Tech Spec Pages for Amendments 243 and 237 Regarding Single Supply Header Operation of the Buried Nuclear Service Water System ML0819801982008-07-14014 July 2008 Proposed Technical Specification Amendment, Technical Specification 3.6.6, Containment Spray System; 3.7.5, Auxiliary Feedwater System ML0813000352008-05-28028 May 2008 Tech Spec Pages for Amendments 241 and 236 Regarding Changes to the Update Final Safety Analysis Report 2024-05-23
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Text
Duke JAMES R. MORRIS, VICE PRESIDENT rEnergyo Duke Energy Carolinas, LLC Carolinas Catawba Nuclear Station 4800 Concord Road / CN01 VP York, SC 29745 803-701-4251 803-701-3221 fax September 30, 2009 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (DEC)Catawba Nuclear Station (CNS), Units 1, and 2 CNS Docket Nos. 50-413, 50-414 McGuire Nuclear Station (MNS), Units 1, and 2 MNS Docket Nos.50-369, 50-370 Oconee Nuclear Station (ONS), Units 1,2, and 3 ONS Docket Nos.50-269, 50-270, 50-287 License Amendment Request (LAR) "Catawba and McGuire Containment Spray Nozzle and Oconee Reactor Building Spray and Cooling Systems Technical Specification Surveillance Requirement" In accordance with the provisions of Section 50.90 of Title 10 of the Code of Federal Regulations, DEC is submitting a request for amendment to the Technical Specifications (TS)for CNS Units 1 and 2, MNS Units 1 and 2, and ONS Units 1, 2, and 3. The proposed license amendment request revises the surveillance frequency associated with containment spray nozzle testing. Currently the testing for nozzle blockage is performed every ten years. DEC is proposing to change this frequency to "following activities that could result in nozzle blockage." Enclosure 1 provides a description and assessment of the proposed changes. In addition to: Attachment 1 contains the Technical Specifications (Mark-Up) and Attachment 2 contains the Technical Specification Bases (Mark-Up) for all three nuclear sites.Supporting changes will be made to the TS Bases in accordance with TS 5.5.14 (CNS and MNS), and TS 5.5.15 (ONS), "Technical Specifications (TS) Bases Control Program." The affected TS Bases markup is included in Attachment
- 2. These pages are being submitted for information only and do not require issuance by the NRC.DEC requests approval of the proposed license amendment by July 31, 2010 for the upcoming CNS Unit 2 refueling outage. DEC is requesting a standard 30-day implementation grace period to implement this license amendment.
Implementation of this proposed amendment to the Catawba, McGuire, and Oconee TS will not impact each sites respective Updated Final Safety Analysis Report (UFSAR).www. duke-energy.
com U.S. Nuclear Regulatory Commission September 30, 2009 Page 12 This LAR has been reviewed and approved by the respective CNS, MNS, and ONS Plant Operations Review Committee (PORC), and the Corporate Nuclear Safety Review Board.In accordance with 10 CFR 50.91, a copy of this application with enclosure and attachments, is being provided to the designated North Carolina and South Carolina state officials.
There are no new regulatory commitments contained in this LAR. Inquiries on this matter should be directed to Adrienne F. Driver at 803.701.3445.
Sincerely, James R. Morris Site Vice President, Catawba Nuclear Station
Enclosure:
- 1. Basis for Proposed Changes Attachments:
- 1. CNS, MNS, ONS TS Changes (Mark-up)2. CNS, MNS, ONS TS Bases Changes (Mark-Up)
U.S. Nuclear Regulatory Commission September 30, 2009 Page 13 Mr. James R. Morris affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowledge.
James RLlMorris, CNS Site Vice President Subscribed and sworn to me: "/Dae"& ýj Notary 2ý61ic A &- -dj ! ýMy Commission Expires: Date SEAL U.S. Nuclear Regulatory Commission September 30, 2009 Page 14 xc w/Enclosures and Attachments:
U.S. Nuclear Regulatory Commission Luis A. Reyes, NRC Region II Administrator U.S. Nuclear Regulatory Commission
-Region I1 Atlanta Federal Center 61 Forsyth St., SW, Suite 23 T85 Atlanta, Georgia 30303-8931 Mr. J.F. Stang, Jr., NRC Senior Project Manager (ONS)U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation One White Flint North, Mail Stop 8 G9A Rockville, MD 20852-2738 Mr. Jon H. Thompson, NRC Project Manager (CNS and MNS)U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation 11555 Rockville Pike, Mail Stop 8 G9A Rockville, MD 20852-2738 Mr. GA. Hutto, NRC Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station Mr. A.T Sabisch, NRC Senior Resident Inspector U.S. Nuclear Regulatory Commission Oconee Nuclear Station Mr. J. Brady, NRC Senior Resident Inspector U.S. Nuclear Regulatory Commission McGuire Nuclear Station State of South Carolina Official S.E. Jenkins, Section Manager Division of Waste Management S.C. Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 State of North Carolina Official BO. Hall, Section Chief Division of Environmental Health, Radiation Protection Section North Carolina Department of Environment and Natural Resources 1645 Mail Service Center Raleigh, NC 27699 U.S. Nuclear Regulatory Commission September 30, 2009 Page 15 bxc w/Enclosures and Attachments:
Lisa F. Vaughn R.D. Hart, CNS RGC Manager K.L. Ashe (MGO1RC)Bob Meixell (ON03RC)NCMPA-1, CNS Owner NCEMC, CNS Owner PMPA, CNS Owner R.L. Gill, NRI&IA Manager (EC05P)ELL-EC050 RGC Date File Catawba Document Control File 801.01 McGuire Document Control File 801.01 Oconee Document Control File 801.01 O Duke Energy Fleet-Wide Licensing Amendment Request September 2009 A The proposed amendment will modify the surveillance requirements CNS SR 3.6.6.7, MNS SR 3.6.6.7, and ONS SR 3.6.5.8 for each respective nuclear station's containment/reactor building spray system.Catawba Nuclear Station, Regulatory Compliance Catawba Nuclear Station McGuire Nuclear Station Oconee Nuclear Station 0 Enclosure 1 Basis for Proposed Changes
1.0 DESCRIPTION
This is a request to amend Facility Operating Licenses NPF-35, NPF-52, NPF-9, NPF-17,. DPR-38, DPR-47, and DPR-55 for Catawba Nuclear Station (CNS) Units 1 and 2, McGuire Nuclear Station (MNS) Units 1 and 2, and Oconee Nuclear Station (ONS) Units 1, 2, and 3 respectively.
The proposed changes will allow performance of testing for nozzle blockage following activities which could result in nozzle blockage, rather than a fixed periodic basis. Currently the testing for nozzle blockage is performed every ten years.This change is being requested to reflect industry operating experience and plant specific experience and practices.
The proposed amendment will modify the surveillance requirement (SR) CNS SR 3.6.6.7, MNS SR 3.6.6.7, and ONS SR 3.6.5.8 for each respective nuclear station's containment/reactor building spray system as follows: Current SURVEILLANCE FREQUENCY.
SR .Verify each spray nozzle is unobstructed.
110 years Revised SURVEILLANCE FREQUENCY SR Verify each spray nozzle is unobstructed.
Following activities which could result in blockage.El- 2 Catawba Nuclear Station. Enclosure 1 McGuire Nuclear Station'Oconee Nuclear Station Basis for Proposed Changes 2.0 Background Currently the surveillance requires verification every ten years that the containment spray nozzles are unobstructed.
The NRC has recognized that nozzle flow testing at this frequency is not necessary due to the design of the system.In the development of NUREG-1366 "Improvements to Technical Specifications Surveillance Requirements", the NRC found that problems in pres.surized water reactor containment spray systems were construction related. In response to this conclusion, many nuclear power plants have requested, and the NRC has granted, license amendments to revise their containment spray nozzles surveillance frequency to"following activities which could result in nozzle blockage." 2.1 System Description CNS Containment Spray System Description The containment spray system is designed to remove thermal energy from the containment atmosphere in the event of a loss-of-coolant accident (LOCA) and maintain containment pressure below the containment design limit of 15 psig after all the ice in the ice condenser has melted. The containment spray system consists of two independent trains. The containment spray nozzles are located on six spray ring headers which are located high in the upper containment to maximize the spray fall height.The containment spray system consists of two spray pumps and two spray heat exchangers in parallel, with associated piping, valves, and spray ring headers per unit. One train is defined as one spray pump with spray heat exchanger and partial flow from one Residual Heat Removal (RHR) pump with a heat exchanger.
The stainless steel nozzles are of hollow cone ramp bottom design. These nozzles have an approximately 3/8 inch spray orifice and are not subject to clogging by particles less than 1/4 inch in maximum dimension.
During the recirculation phase of operation, fluid is screened through perforated plates with 3/32 inch openings and pumped to the El- 3 Catawba Nuclear Station Enclosure 1 McGuire Nuclear-Station Oconee Nuclear Station Basis for Proposed Changes nozzles. The nozzles and ring headers are positioned to maximize coverage of the Containment volume from each set of spray ring headers.MNS Containment Spray System Description The containment spray system is designed to remove thermal energy from containment in the event of a LOCA or a main steam line break (MSLB). It performs this function in conjunction.with the Emergency Core Cooling System (ECCS), which subcools the reactor by direct injection.
The heat removal capability of the spray system keeps the containment pressure below the design pressure of 15 psig after all the ice has melted, while steam generation in the core continues to enter the containment.
The system also serves to remove fission product iodine from the post-accident containment atmosphere.
The containment spray system consists of two spray pumps and two spray heat exchangers in parallel, with associated piping, valves, and spray ring headers per unit. One spray train is defined as one spray pump with spray heat exchanger and partial flow from one Residual Heat Removal (RHR) pump with a heat exchanger.
The stainless steel nozzles are of hollow cone ramp bottom design. These nozzles have an approximately 3/8 inch spray orifice and are not subject to clogging by particles less than 1/4 inch in maximum dimension.
During the recirculation phase of operation, fluid is screened through perforated plates with 3/32 inch openings and pumped to the nozzles. The nozzles and spray ring headers are positioned to maximize coverage of the Containment volume from each set of spray ring headers.ONS Reactor Building Spray System Description The ONS Unit 1, 2 and 3 Reactor Building Spray (RBS)Systems are designed to activate upon receipt of high Reactor Building pressure.
The RBS system removes sensible and latent heat from the containment atmosphere; additionally, operation of the RBS system serves to entrain fission product iodine into the spray water, thereby reducing possible iodine leakage to the environment.
El-4 Catawba Nuclear Station Enclosure 1 McGuire Nuclear Station Oconee Nuclear Station Basis for Proposed Changes The RBS consists of two independent trains. Each train consists of one RBS pump, which initially takes suction from the Borated Water Storage Tank (BWST) via the Low Pressure Injection (LPI) suction piping, and discharges through a throttle valve to its respective RBS nozzle header at the Reactor Building dome following a high energy line break. Upon depletion of the BWST level to a specified setpoint, the Reactor Building Sump will provide water for the spray pumps by manual operator action.The RBS spray headers are two full-coverage, overlapping stainless steel headers located near the Reactor Building dome. Each header size reduces from eight inches to six inches to four inches as it spreads across the Reactor Building dome. The containment spray nozzles are stainless steel sized and can pass particles up to approximately 1/8 inch diameter.3.0 Foreign Material Exclusion (FME) Program The fleet-wide FME program at Duke Energy Carolinas, LLC (DEC) is governed by approved work control procedures.
These procedures ensure that the appropriate precautions are taken as needed to minimize the inadvertent and uncontrolled introduction of foreign materials into plant systems and components.
FME training is required for all personnel performing work planning activities, maintenance, modifications, repairs, testing, or inspections on plant equipment and components.
Breached fluid or piping systems are required to be coveted when not being directly accessed for .inspection or maintenance.
Administrative FME controls also delineate program requirements for maintaining cleanliness of plant systems and components.
For example, for maintenance activities that create debris, cleanliness inspections are required.
For safety class systems and components, the final cleanliness inspection is performed by quality control inspectors.
El- 5 Catawba Nuclear Station Enclosure 1 McGuire Nuclear Station Oconee Nuclear Station Basis for Proposed Changes If FME integrity is lost through the intrusion or discovery of foreign material, procedures direct the worker(s) to enter the issue into the Corrective Action Program.4.0 Technical Evaluation The proposed amendment will modify CNS SR 3.6.6.7, MNS SR 3.6.6.7, and ONS SR 3.6.5.8 to change the frequency for verifying spray nozzles are unobstructed.
Currently, the surveillance requires the verification of containment spray nozzle operability to be performed every ten years and the CNS and MNS Technical Specification Bases describe the operability verification is performed by blowing low pressure air or smoke through the nozzles, or using a vacuum blower to verify flow. Generic Letter 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation," dated September 27, 1993, and NUREG-1366"Improvements to Technical Specifications Surveillance Requirements", dated December 1992 were used as the basis for requesting a change to the CNS, MNS, and ONS 10-year surveillance frequency due to the stainless steel construction of the nozzles and piping. No coating materialwhich could potentially cause clogging of the spray nozzles, similar to that used on carbon steel piping, is used in the piping or nozzles at CNS, MNS, and ONS. DEC proposed to revise the current periodic frequency for spray nozzle operability verification with a qualifying statement that would identify that operability verification is required following "activities that could cause nozzle blockage." Since containment spray header or nozzle activities occur infrequently, the proposed surveillance frequency should result in less spray nozzle testing.The spray nozzles are a passive system. The greatest potential for introduction of debris that could result in blocking of the nozzles is during maintenance activities on the spray header or nozzles. The nozzles are located at the upper elevations of containment, further reducing the potential of foreign material intrusion.
However, the FME program contains the appropriate level of controls to provide a high level of confidence that foreign materials El-6 Catawba Nuclear Station Enclosure 1 McGuire Nuclear Station Oconee Nuclear Station Basis for Proposed Changes will not be introduced when containment spray system boundaries are breached for maintenance or testing activities on the spray header or nozzles. The need to test for nozzle blockage following maintenance activities is currently addressed by the post-maintenance testing program which evaluates work scope to determine appropriate retests. However, unanticipated activities such as inadvertent spray actuation, a major configuration change, or a loss of foreign material control when working within the respectivesystem boundary, may require surveillance performance.
The containment spray headers are maintained dry above the FWST (CNS, and MNS) and BWST (ONS) static height.Additionally, during pump testing, the spray nozzles are isolated from system flow, therefore minimizing the potential for boric acid accumulation.
However, should there be inadvertent fluid flow through the nozzles, such as the result of spurious actuation; DEC would evaluate testing to determine if the nozzles have remained unobstructed.
4.1 Testing The inspection and testing requirements for the containment spray system are described in their respective Updated Final Safety Analysis (UFSAR) section, CNS 6.2.2.4, MNS 6.5.4, and ONS 6.2.2.4.For the initial spray header flow verification pre-operational test, each spray nozzle in all the spray headers was checked for unobstructed flow. The tests were performed using low pressure air blown through the test connections or a vacuum blower to verify flow. Actual flow rate is measured using an air velocity meter for MNS periodic testing in addition to visual observation.
CNS and ONS continue to perform visual observation with low pressure air blown through test connections.
Periodic air flow tests through the spray nozzles have been conducted at the interval specified in TS. Air flow is then verified through each associated spray nozzle.El- 7 0* Enclosure I Catawba Nuclear Station McGuire Nuclear Station Oconee Nuclear Station Basis for Proposed Changes The spray follows: nozzle test history for CNS, MNS and ONS is as Station Unit Test Date RFO/Pre-OPS MNS 1 1980 Pre-operational MNS 2 1983 Pre-operational MNS 1 1986 PERIODIC MNS 2 1987 Periodic MNS .1 1990 Periodic MNS 2 1992 Periodic MSN 1 1998 Periodic MNS 2 2000 Periodic MNS 1 2007 Periodic CNS 1 1983 Pre-operational CNS 2 1985 Pre-operational CNS 1 1988 Periodic CNS 2 1990 Periodic CNS 1 1999 Periodic CNS 2 1998 Periodic ONS 1 1972 Pre-operational ONS 2 1973 Pre-operational ONS 3 1974 Pre-operational ONS 1 1977 Periodic ONS 2 1978 Periodic ONS 3 1979 Periodic-ONS 1 1981 Periodic ONS 2 1982 Periodic ONS 3 1984 Periodic ONS 1 1990 Periodic ONS 2 1990 Periodic ONS 3 1992 Periodic ONS 1 1994 Periodic ONS 2 1999 Periodic ONS 3 2001 Periodic ONS 1 .2002' Periodic ONS 2 2008 Periodic ONS 3 2004 Periodic El- 8 Catawba Nuclear Station Enclosure I McGuire Nuclear Station Oconee Nuclear Station Basis for Proposed Changes The results of each test demonstrated unobstructed flow through each nozzle.4.2 Maintenance History CNS Maintenance History On January 3, 1984 for pre-operational testing, flow was inadvertently established through the lB train of the Containment Spray Ring. The question was addressed as to whether that spray ring should be retested to verify a flow path to each nozzle due to the possible crystallization of the boric acid solution that was sprayed. Analysis was performed and it was determined that there was no possibility of flow blockage of the lB train due to this inadvertent spray and a retest was not required to verify this. Following this inadvertent spray, all subsequent testing of the containment spray nozzles were met satisfactorily and there has been no blockage of any kind.During performance of surveillance on December 6, 1988 no flow was detected on nozzle #39 on the lB header.Maintenance inspected the nozzle and found no blockage.The nozzle was retested successfully two days later. The discrepancy sheet states that the test equipment may not have been oriented properly during the first attempt to verify air flow. The next surveillance showed no indication of any blockage.In the aforementioned event of inadvertent spray described above for CNS Unit 1, all subsequent testing of the containment spray nozzles has been satisfactory, and there has been no identified blockage of any kind. There has been no history of events identified of inadvertent spray through the containment spray nozzles on Unit 2 at CNS.A review of the maintenance history of the CNS Unit 1 and Unit 2 containment spray nozzles and spray ring headers was performed to determine the work that took place since the most recent surveillance tests on the system. A review of the maintenance work orders identified no work activities El-9 Catawba Nuclear Station Enclosure 1 McGuire Nuclear Station Oconee Nuclear Station Basis for Proposed Changes on the containment spray nozzles and spray ring headers since the most recent flow tests were performed.
There have been no occurrences of inadvertent flow through the spray nozzles subsequent to the performance of the last nozzle flow tests.MNS Maintenance History A review of the maintenance history of the MNS Unit 1 and Unit 2 containment spray nozzles and spray ring headers was performed to determine the work that took place since the most recent survieillance tests on the system. A review Of the maintenance work orders identified no maintenance or modification activities were conducted which could have introduced foreign material into the containment spray nozzles and spray ring headers since the most recent flow tests were performed.
There have been no historic work activities beyond the most recent periodic test that identified the potential for foreign material intrusion.
There have been no occurrences of inadvertent flow through the spray nozzles subsequent to the performance of the last nozzle flow tests.ONS Maintenance History On-October 17, 1974, ONS Unit 2 was in cold shutdown with the LPI system in service for decay heat removal (DHR)operations.
Preparations were being made to begin Reactor Coolant System (RCS) heat up. These'preparations included placing Reactor Building Spray in Engineered Safeguards (ES) alignment.
After opening 2BS-4, the Unit 2 Reactor Building fire alarm activated in the Unit 2 Control Room.Control Room Operators subsequently noted a sharp decrease in Pressurizer level and an increase in Reactor Building Normal Sump level. Operator actions were taken to close 2BS-3 and 2BS-4 to stop the loss of inventory.
Subsequent investigation found valve 2BS-2 (B RBS train discharge valve) partially open although it indicated fully closed in the control room. The erroneous indication was due to an improperly configured limit switch in valve 2BS-2. The Reactor Building fire alarm activated when water from the spray header shorted out detector units. Approximately 200 gallons of water was-sprayed into the Unit 2 Reactor Building.El- 10 Catawba Nuclear Station Enclosure 1 McGuire Nuclear. Station Oconee Nuclear Station Basis f6r Proposed Changes On March 29, 1977, technicians were performing online testing of ES Channel 5 on ONS Unit 3 when ES Channel 7 inadvertently tripped...
Actuation of ES Channel 7 caused the 3A RBS pump to start and the normally-closed downstream isolation valve (3BS-1) to open. The pump operated for approximately 41 seconds before being secured by control room operators.
Operators were dispatched to thereactor building to check for water damage. No signs of water damage were noted. Approximately 1300 gallons of water was sprayed into the Unit 3 Reactor Building.On November 9, 1989, ONS Unit 3 was being shutdown for refueling and preparations were being made to begin decay heat removal (DHR) with LPI system. At the time DHR was being initiated, the suction of the 3A RBS train was still aligned to the LPI system through open valve 3BS-3 (3A Reactor Building Spray Pump Suction Isolation valve).During alignment of the LPI system to the RCS, Control Room Operators identified indications of RCS leakage.Subsequent investigation determined that valve 3BS-1 (3A RBS Header Discharge Isolation valve); located on the, discharge of the 3A RBS train was partially open when it indicated closed. RCS pressure forced water through the 3A RBS train, through partially open valve 3BS-1, and out the spray nozzles of the 3A RBS train. It was determined that valve 3BS-1 had not been fully closed following stroke.testing on October 12, 1989 due to problems with valve position indications.
Approximately 2000 gallons of water was sprayed into the Unit,3 Reactor Building.In the aforementioned three events of inadvertent spray described above for ONS Units 2 and 3, all subsequent testing of the containment spray nozzles has been satisfactory, and there has been no identified blockage of any kind. There has been no history of events identified of inadvertent spray through the reactor building containment spray nozzles on Unit 1 at ONS. Additionally, there have been no occurrences of inadvertent flow through the spray nozzles subsequent to the performance of the last nozzle flow tests.El- 11 Catawba Nuclear Station W Enclosure I McGuire Nuclear Station Oconee Nuclear Station Basis for Proposed Changes Modifications were performed during refueling outages lEOC2l fall 2003, 2EOC19 fall 2002, and 3EOC20 spring 2003.These modifications plugged approximately half of the nozzles on each train to improve RBS pump net positive suction head. Upon completion of the modifications, FME controls were credited along with double verification to ensure no FME was introduced into the spray header(s).
Nozzle locations that were not deactivated were not disturbed during the modification implementation.
A review of the maintenance history of the ONS Unit 1, 2 and 3 RBS system was performed to determine the work that took place since the most recent surveillance tests on the system. With respect to the aforementioned modifications, there has been no work activities conducted on the containment spray nozzles and spray headers.The proposed amendments are expected to reduce unneeded surveillance testing of the spray nozzles. Thorough inspection and flow testing were performed for the spray systems during the preoperational tests. Subsequent periodic flow test results have indicated no nozzles were obstructed.
The spray nozzles are a passive component and the most likely introduction of nozzle blockage would occur during maintenance activities.
FME controls provide assurance that the potential for nozzle obstruction will continue to be low by providing protection against the introduction of foreign materials into open piping. Should foreign material with the potential to obstruct the spray nozzles be discovered in a portion of the system, the corrective action program will direct that the extent of condition be evaluated, and cleanliness restored and determine if surveillance testing is required.4.3 Summary In review of the maintenance history, testing and system modifications above in section 4.2 there have been no significant maintenance or modification activities that have been identified which could have potentially caused El- 12 Catawba Nuclear Station Enclosure I McGuire Nuclear Station Oconee Nuclear Station Basis for Proposed Changes nozzle blockage, thus requiring continual periodic testing at CNS, MNS, or ONS. This change is being requested based on industry and plant experience which indicates blockage of the containment spray nozzles during normal plant operation is unlikely.
This proposed change eliminates unnecessary testing of the spray nozzles. Testing would be performed based on activities or conditions that could potentially cause nozzle blockage.
The surveillance requires workers to verify air flow at each nozzle located at high elevations inside containment, and the potential reduction in the frequency of performance should enhance personnel safety. Similarly, the proposed changes are expected to result in a reduction in personnel exposure and outage costs associated with performing airflow tests.Industry and plant specific experience has shown that the proposed change more accurately reflects when verification of spray nozzle operability is appropriate.
5.0 REGULATORY ANALYSIS 5.1 No Significant Hazards Consideration The proposed amendment will modify CNS SR 3.6.6.7, MNS SR 3.6.6.7, and ONS SR 3.6.5.8 to change the frequency for verifying spray nozzles are unobstructed.
The surveillance is being changed from a 10 year interval to a performance-based frequency.
Specifically, the verification of no nozzle obstruction would only be performed following activities that could subject the system to possible sources of nozzle blockage.
The proposed change is considered to be more reflective of plant operating experience, which has demonstrated that the introduction of spray nozzle blockage during normal plant operation is unlikely.Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
El- 13 Catawba Nuclear Station Enclosure 1 McGuire Nuclear Station Oconee Nuclear Station Basis for Proposed Changes No. The proposed amendment will modify CNS SR 3.6.6.7, MNS SR 3.6.6.7, and ONS SR 3.6.5.8 to change the frequency for verifying spray nozzles are unobstructed.
The proposed change modifies the frequency for performance of a surveillance test which does not impact any failure modes that could lead to an accident.
The proposed frequency change does not affect the ability of the spray nozzles or spray system to perform its accident mitigation function as assumed and therefore there is no effect on the consequence of any accident.
Verification of no blockage continues to be required, but now verification will be performed following activities that could result in nozzle blockage.Based on this discussion, the proposed amendment does not increase the probability or consequence of an accident previously evaluated.
Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
No. The proposed amendment will modify CNS SR 3.6.6.7, MNS SR 3.6.6.7, and ONS SR 3.6.5.8 to change the frequency for verifying spray nozzles are unobstructed.
The spray systems are not being physically modified and there is no impact on the capability of the system to perform accident mitigation functions.
No system setpoints are being modified and no changes are being made to the method in which borated water is delivered to the spray nozzles. The testing requirements imposed by this proposed change to check for nozzle blockage following activities that could cause nozzle blockage do not introduce new failure modes for the system. The proposed amendment does not introduce accident initiators or malfunctions that would cause a new or different kind of accident.
Therefore, the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
Does the proposed change involve a significant reduction in a margin of safety?El-14 Catawba Nuclear Station Enclosure 1 McGuire Nuclear Station Oconee Nuclear Station Basis for Proposed Changes No. The proposed amendment will modify CNS SR 3.6.6.7, MNS SR 3.6.6.7, and ONS SR 3.6.5.8 to change the frequency for verifying spray nozzles are unobstructed.
The proposed change does not change or introduce any new setpoints at which mitigating functions are initiated.
No changes to the design parameters of the spray systems are being proposed.
There are no changes in system operation being proposed by this change that would impact an established safety margin. The proposed change modifies the frequency ,for verification of nozzle operability in such a way that continued high confidence exists that the spray systems will continue to function as designed.
Therefore, based on the above, the proposed amendment does not involve a significant reduction in a margin of safety..5.2 Applicable Regulatory Requirements/Criteria Catawba, McGuire and Oconee Nuclear Station facility operating licenses complies with the standards and requirements of the, Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I , and all required notifications to other agencies or bodies duly made. The Principle Design Criteria (PDC) for Oconee Units 1, 2, and 3 were developed in consideration of the seventy General Design Criteria for Nuclear Power Plant Construction Permits proposed by the Atomic Energy Commission in a proposed rule-making published for 10 CFR Part 50 in the Federal Register of. July 11, 1967.Catawba and McGuire Nuclear Station's applicability and compliance is in accordance with 10 CFR 50 Appendix A, General Design Criteria (GDC) for Nuclear Plants. The table below provides the GDC or PDC associated with the containment spray systems for CNS, MNS, and ONS that are applicable to the proposed changes within this license amendment request.General Design Criterion Principle Design Criterion#16- "Containment Design" #70 -"Control of Releases of Radioactivity to the Environment" (Category B)El-15 0.Enclosure I Catawba Nuclear Station McGuire Nuclear Station Oconee Nuclear Station Basis for Proposed Changes#38 -"Containment Heat Removal"#39 -"Inspection of Containment Heat Removal System"#40 -"Testing of Containment Heat Removal System"#42 -"Testing of Containment Atmosphere Cleanup Systems"#52 -"Containment Heat Removal Systems" (Category A)#45 -"Inspection of Emergency Core Cooling Systems (Category A)#46 -"Testing of Emergency Core Cooling Systems (Category A)#49 -"Containment Design Basis" (Category A)#50 -Basis""Containment Design In review of the GDCs and PDCs the proposed amendment to the surveillance requirement frequency change does not impact the conformance to the above applicable design criteria.5.3 NRC Commitments There are no new regulatory commitments contained in this LAR.5.4 Conclusions DEC has evaluated the aspects of the proposed changes to the Technical Specifications to determine whether or not the change involves a significant hazards consideration under the standards set forth in 10 CFR 50.92.Accordingly, DEC concludes that the changes do not meet any of the three criteria for a significant hazards consideration.
5.5 Precedents The NRC has modified the technical specifications of other United States nuclear power reactors to revise their El7 16 Catawba Nuclear Station 0 Enclosure 1 McGuire Nuclear Station Oconee Nuclear Station Basis for Proposed Changes containment spray nozzles surveillance frequency to"following activities which could result in nozzle blockage", as noted in the following table.Reactor NRC Approval Date Accession No.Millstone Power March 2008 ML070880705 Station Unit 2 Ginna Nuclear July 31, 2006 ML061980055 Power Station 6.0 ENVIRONMENTAL EVALUATION A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement.
However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may *be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c) (9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
El- 17
.Enclosure 1 Catawba Nuclear Station McGuire Nuclear Station Oconee Nuclear Station Basis for Proposed Changes
7.0 REFERENCES
- 1. Catawba Nuclear Station Updated Final Safety Analysis, Chapter 6 "Engineered Safety Features", November 15, 2007 2. McGuire Nuclear Station Updated Final Safety Analysis, Chapter 6 '"Engineered Safety Features", April 13, 2008 3. Oconee Nuclear Station Updated Final Safety Analysis, Chapter 6 "Engineered Safeguards", December 31, 2007 4. NUREG-1366, "Improvements to Technical Specifications Surveillance Requirements", December 1992 5. Generic Letter 93-05 "Line-Item Technical Specifications Improvements For Testing During Power Operation", September 27, 1993 El- 18 0 6I ATTACHMENT 1 TECHNICAL SPECIFICATIONS (MARK UP)
Containont Spray System 3.6.6 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.6.2 Verify each containment spray pump's developed head at In accordance with the flow test point is greater than or equal to the required the Inservice developed head. Testing Program SR 3.6.6.3 Verify each automatic containment spray valve in the flow 18 months path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.SR 3.6.6.4 Verify each containment spray pump starts automatically 18 months on an actual or simulated actuation signal.SR 3.6.6.5 Verify that each spray pump is de-energized and 18 months prevented from starting upon receipt of a terminate signal and is allowed to start upon receipt of a start permissive from the Containment Pressure Control System (CPCS).SR 3.6.6.6 Verify that each spray pump discharge valve closes or is 18 months prevented from opening upon receipt of a terminate signal and is allowed to open upon receipt of a start permissive from the Containment Pressure Control System (CPCS).SR 3.6.6.7 Verify each spray nozzle is unobstructed.
1O-years Following Activities which could result in nozzle blockage Catawba Units 1 and 2 3.6.6-2 Amendment Nos. 1t-7466-Contain t Spray System 3.6.6 SURVE"ILLANCE FREQUENCY SR 3.6.6.2 Verify each containment spray pump's developed head at In accordance with the flow test point is greater than or equal to the required the Inservice developed head. Testing Program SR 3.6.6.3 Verify each automatic containment spray valve in the flow 18 months.path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.SR 3.6.6.4 Verify each containment spray pump starts automatically 18 months on an actual or simulated actuation signal.SR 3.6.6.5 Verify that each spray pump is de-energized and 18 months prevented from starting upon receipt of a terminate signal and is allowed to start upon receipt of a start permissive from the Containment Pressure Control System (CPCS).SR 3.6.6.6 Verify that each spray pump discharge valve closes or is 18 months prevented from opening upon receipt of a terminate signal and is allowed to open upon receipt of a start permissive from the Containment Pressure Control System (CPCS).SR 3.6.6.7 Verify each spray nozzle is unobstructed.
10 -yeaFs Following activities which could result in nozzle blockage McGuire Units 1 and 2 3.6.6-2 Amendment Nos. 184/166 1 9 Reactor Building Spray and Cooling Systems 3.6.5 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.5.5----------------
NOTE--------------
Applicable for RB cooling system after the completion of the LPSW RB Waterhammer Modification on the respective Unit.Verify each automatic reactor building spray and cooling valve in each required flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.18 months SR 3.6.5.6 Verify each required reactor building spray 18 months pump starts automatically on an actual or simulated actuation signal.SR 3.6.5.7 Verify each'required reactor building cooling 18 months train starts automatically on an actual or simulated actuation signal.SR 3.6.5.8 Verify each spray nozzle is unobstructed.
Following activities which could result in nozzle blockage.
10--yeaFs OCONEE UNITS 1, 2, & 3 3.6.5-6 Amendment Nos. 363, 365, &
ATTACHMENT 2: TECHNICAL BASES SPECIFICATIONS (MARK UP) 0 Conta ent Spray System B 3.6.6 BASES SURVEILLANCE REQUIREMENTS (continued) testing in this fashion.SR 3.6.6.6 deals solely with containment spray header containment isolation valves NS12B, NS15B, NS29A, and NS32A. It must be shown through testing that: (1) each valve closes when the CPCS permissive is removed, OR (2) each valve is prevented from opening in the absence of a CPCS permissive.
In addition to one of the above, it must also be shown that each valve opens when given a CPCS permissive.
The 18 month Frequency is appropriate based on the reliability of the components.
SR 3.6.6.7 With the containment spray inlet valves closed and the spray header drained of any solution, low pressure air or smoke can be blown through test connections.
The spray nozzles can also be e.:iedo,,.
tested using a vacuum blower to induce air flow through each nozzle to verify unobstructed flow. This SR ensures that each spray nozzle is unobstructed and that spray coverage of the containment during an accident is not degraded.
Because of the passive design of the nozzle, a test at 10Q year intervals is considered adequate to) detect obstruction oe the spray nozzles. This SR requires verification that each spray nozzle is unobstructed following activities that could cause nozzle blockage.
Normal.plant operation and activities are not expected to initiate this SR. However activities such as inadvertent spray actuation that causes fluid flow through the nozzles, major configuration change, or a loss of foreign material control when working within the respective system boundary may require surveillance performance.
REFERENCES
- 1. 10 CFR 50, Appendix A, GDC 38, GDC 39, GDC 40, GDC 41, GDC 42, and GDC 43.2. UFSAR, Section 6.2.3. 10 CFR 50.49.4. 10 CFR 50, Appendix K.5. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).
- 6. ASME, Boiler and Pressure Vessel Code,Section XI.Catawba Units 1 and 2 B 3.6.6-7 Revision No-+-
ContainmQSpray System B 3.6.6 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.6.6.3 and SR 3.6.6.4 These SRs require verification that each automatic containment spray valve actuates to its correct position and each containment spray pump starts upon receipt of an actual or simulated Containment Pressure High-High signal. This Surveillance is not required for valves that are locked, sealed, or otherwise secured in the required position under administrative controls.
The 18 month Frequency is based on the need to perform these Surveillances under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillances were performed with the reactor at power. Operating experience has shown these components usually pass the Surveillances when performed at the 18 month Frequency.
Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
The surveillance of containment sump isolation valves is also required by SR 3.6.6.3. A single surveillance may be used to satisfy both requirements.
SR 3.6.6.5 and SR 3.6.6.6 These SRs require verification that each containment spray pump discharge valve opens or is prevented from opening and each containment spray pump starts or is de-energized and prevented from starting upon receipt of Containment Pressure Control System start and terminate signals. The CPCS is described in the Bases for LCO 3.3.2,"ESFAS." The 18 month Frequency is based on the need to perform these Surveillances under the conditions that apply during a plant outage.SR 3.6.6.7 With the containment spray inlet valves closed and the spray header drained of any solution, low pressure air or smoke can be blown through test connections.
The spray nozzles can also be perediGa14y tested Osing a vacuum blower to induce air flow through each nozzle to verify unobstructed flow. This SR ensures that each spray nozzle is...nnh .tr- w...i. ..nd th-pit iznrn"e .n". .ri. .e-f th' .nnt.ninm.nt H .inn'-.. .. '.. .accident is not degraded.
Because of the passive design of the nez 4e.-,a test at 10 year intervals is considered adequYate to detect obstructioR -Of the spray nozzles. This SR requires verification that each spray nozz e is unobstructed following activities that could cause nozzle blockage.
N rmal plant operation and activities are not expected to initiate this SR. Ho ever activities such as inadvertent spray actuation that causes fluid flow thrbugh McGuire Units 1 and 2 B 3.6.6-6 Revision No[ g3 S ContainmOSpray System B 3.6.6 BASES the nozzles, major configuration change, or a loss of foreign material control when working within the respective system boundary may reqUire surveillance performance./
McGuire Units 1 and 2 B 3.6.6-7 Revision No[ 4a--
Reactor Building Spray, , Cooling Systems.B 3.6.5 BASES SURVEILLANCE REQUIREMENTS SR 3.6.5.8 With the reactor building spray header isolated and drained of any solution, station compressed air is introduced into the spray headers.-e verfy the availability of the headers aid spray nozzles. Perfrmanue of, this Survcillancc demonstratcs that each spray nozzle is unobStrUctcd and provides assurance that spray coverage of the containment during an a,,idont is not degraded-.
This SR requires verification that each spray nozzle is unobstructed following activities which could cause nozzle blockage.
Normal plant operation and activities are not expected to initiate this SR. However activities such as inadvertent spray actuation that causes fluid flow through the nozzles, maior confi-quration chanqe, or a loss of foreiqn material control when working within the respective system boundary may require surveillance performance.
Due to the passive nature of the design of the nozzles, a test at 10 year inteR'als is consider-ed adequate to detect obsio Uctien of the spray nozzles-.REFERENCES
- 1. UFSAR, Section 3.1.2. UFSAR, Section 6.2.3. 10 CFR 50.36.4. ASME, Boiler and Pressure Vessel Code,Section XI.OCONEE UNITS 1, 2, & 3 B 3.6.5-11 Amendment Nos. 363, 365, & 3