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Category:Letter type:BSEP
MONTHYEARBSEP 19-0012, Submittal of 2018 Sea Turtle Annual Report2019-01-17017 January 2019 Submittal of 2018 Sea Turtle Annual Report BSEP 18-0052, Annual Radiological Environmental Operating Report - 20172018-05-10010 May 2018 Annual Radiological Environmental Operating Report - 2017 BSEP 18-0051, Annual Radioactive Effluent Release Report - 20172018-04-26026 April 2018 Annual Radioactive Effluent Release Report - 2017 BSEP 18-0045, Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time2018-04-25025 April 2018 Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time BSEP 18-0054, Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential.2018-04-24024 April 2018 Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential. BSEP 18-0048, Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations2018-04-11011 April 2018 Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D2018-04-11011 April 2018 Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D BSEP 18-0046, Supplement to Response to Request for Additional Information SRXB-RAI-2 Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2018-04-10010 April 2018 Supplement to Response to Request for Additional Information SRXB-RAI-2 Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0047, Supplement to Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) for End of Interval Leakage Test2018-04-0505 April 2018 Supplement to Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) for End of Interval Leakage Test BSEP 18-0041, Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2018-04-0404 April 2018 Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report BSEP 18-0043, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D2018-03-31031 March 2018 Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D BSEP 18-0035, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2018-03-29029 March 2018 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0042, Cycle 22 Core Operating Limits Report (COLR)2018-03-27027 March 2018 Cycle 22 Core Operating Limits Report (COLR) BSEP 18-0040, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for End of Interval Leakage Test2018-03-23023 March 2018 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for End of Interval Leakage Test BSEP 18-0039, Proposed In-Service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay - Nozzles N4A and N4D2018-03-19019 March 2018 Proposed In-Service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay - Nozzles N4A and N4D BSEP 18-0034, Corrected Affidavit Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion2018-03-16016 March 2018 Corrected Affidavit Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0032, Additional Testing Information Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion2018-03-14014 March 2018 Additional Testing Information Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0026, Additional Information Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination2018-03-0707 March 2018 Additional Information Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination BSEP 18-0014, Fifth 10-Year Inservice Testing Program Plan2018-02-19019 February 2018 Fifth 10-Year Inservice Testing Program Plan BSEP 18-0021, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865). Without Proprietary Enclosure2018-02-0505 February 2018 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865). Without Proprietary Enclosure BSEP 18-0017, Revision to Radiological Emergency Response Plan and Implementing Procedure2018-01-30030 January 2018 Revision to Radiological Emergency Response Plan and Implementing Procedure BSEP 18-0015, Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations2018-01-23023 January 2018 Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations BSEP 18-0013, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-01-23023 January 2018 Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control BSEP 18-0001, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2018-01-23023 January 2018 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements BSEP 18-0012, Application to Revise Technical Specifications to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.32018-01-23023 January 2018 Application to Revise Technical Specifications to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 BSEP 18-0009, 2017 Sea Turtle Annual Report2018-01-15015 January 2018 2017 Sea Turtle Annual Report BSEP 17-0098, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2018-01-10010 January 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors BSEP 17-0119, Snubber Program Plan for Fifth 10-Year Interval Inservice Testing Program2018-01-10010 January 2018 Snubber Program Plan for Fifth 10-Year Interval Inservice Testing Program BSEP 17-0115, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-01-0404 January 2018 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control BSEP 17-0110, Seventh Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2017-12-20020 December 2017 Seventh Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions BSEP 17-0121, Post-Examination Documentation and Comments for Operator Retake Initial Examination2017-12-14014 December 2017 Post-Examination Documentation and Comments for Operator Retake Initial Examination BSEP 17-0120, Withdrawal of Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension..2017-12-12012 December 2017 Withdrawal of Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension.. BSEP 17-0118, Supplement to Response to Request for Additional Information Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel..2017-12-0707 December 2017 Supplement to Response to Request for Additional Information Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel.. BSEP 17-0117, Response to Request for Additional Information (Probabilistic Risk Assessment and Human Performance Branches) Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1 AC Sources..2017-12-0606 December 2017 Response to Request for Additional Information (Probabilistic Risk Assessment and Human Performance Branches) Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1 AC Sources.. BSEP 17-0116, Response to Request for Additional Information Regarding Request for Risk- Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of ..2017-12-0404 December 2017 Response to Request for Additional Information Regarding Request for Risk- Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of .. BSEP 17-0104, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination2017-11-29029 November 2017 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination BSEP 17-0111, Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements2017-11-28028 November 2017 Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements BSEP 17-0109, Response to Request for Additional Information Regarding Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times And.2017-11-24024 November 2017 Response to Request for Additional Information Regarding Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times And. BSEP 17-0108, Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements2017-11-22022 November 2017 Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements BSEP 17-0017, Submittal of Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material2017-11-15015 November 2017 Submittal of Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material BSEP 17-0100, Fifth 10-Year Inservice Testing Interval2017-11-0202 November 2017 Fifth 10-Year Inservice Testing Interval BSEP 17-0089, Updates to Request for License Amendment Regarding Core Flow Operating Range Expansion2017-11-0101 November 2017 Updates to Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 17-0093, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2017-11-0101 November 2017 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 17-0078, Request for License Amendment - DC Sources - Operating Surveillance Requirement (SR) 3.8.4.52017-10-0303 October 2017 Request for License Amendment - DC Sources - Operating Surveillance Requirement (SR) 3.8.4.5 BSEP 17-0076, Registration for Use of General License Spent Fuel Casks2017-09-0606 September 2017 Registration for Use of General License Spent Fuel Casks BSEP 17-0081, Revision to Radiological Emergency Response Plan Implementing Procedures2017-09-0505 September 2017 Revision to Radiological Emergency Response Plan Implementing Procedures BSEP 17-0039, Submittal of Response to Inspection Report 05000324/2015404 and 05000325/2015404, Dated March 30, 2015, Inspection of Interim Cyber Security Milestones 1-7 and Target Set Requirements2017-08-15015 August 2017 Submittal of Response to Inspection Report 05000324/2015404 and 05000325/2015404, Dated March 30, 2015, Inspection of Interim Cyber Security Milestones 1-7 and Target Set Requirements BSEP 17-0071, ISFSI - Registration for Use of General License Spent Fuel Casks2017-08-15015 August 2017 ISFSI - Registration for Use of General License Spent Fuel Casks BSEP 17-0064, Application of Dissimilar Metal Weld Full Structural Overlay on Reactor Pressure Vessel Nozzle N92017-07-10010 July 2017 Application of Dissimilar Metal Weld Full Structural Overlay on Reactor Pressure Vessel Nozzle N9 BSEP 17-0060, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-06-29029 June 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. 2019-01-17
[Table view] Category:Technical Specification
MONTHYEARRA-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-22-0110, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf.2022-03-25025 March 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. 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-21-0272, Supplement to 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 4b2021-11-0101 November 2021 Supplement to 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-18-0183, 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 4b2021-04-0101 April 2021 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 ML20342A3472021-03-0404 March 2021 Issuance of Amendment Nos. 303 and 331 Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control Enhancements RA-19-0431, Application to Revise Technical Specifications to Adopt TSTF 564, Safety Limit MCPR2020-03-0909 March 2020 Application to Revise Technical Specifications to Adopt TSTF 564, Safety Limit MCPR 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-19-0157, Supplement to Request for License Amendment Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time2019-03-26026 March 2019 Supplement to Request for License Amendment Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time ML18298A0782018-12-0303 December 2018 2nd Correction to Issuance of Amendments to Adopt Technical Specifications Task Force 542, Revision 2, Reactor Pressure Vessel Water Inventory Control RA-18-0079, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-08-14014 August 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO BSEP 18-0045, Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time2018-04-25025 April 2018 Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time BSEP 18-0012, Application to Revise Technical Specifications to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.32018-01-23023 January 2018 Application to Revise Technical Specifications to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 BSEP 18-0001, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2018-01-23023 January 2018 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements BSEP 18-0013, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-01-23023 January 2018 Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process ML16252A2202016-08-29029 August 2016 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 BSEP 16-0067, Technical Specification Bases, Rev 882016-08-0303 August 2016 Technical Specification Bases, Rev 88 ML16224A2832016-08-0303 August 2016 Technical Specification Bases, Rev 88 BSEP 16-0047, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program2016-06-29029 June 2016 Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016 Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process ML15175A4452015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6 ML15175A4482015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6 ML15175A4472015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6 ML15175A4422015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 3 of 6 RA-15-0006, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 62015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 6 ML12237A0532012-08-14014 August 2012 Technical Specification Bases, Brunswick Steam Electric Plant, Unit 1 - Renewed Facility Operating License DPR-71, Revision 80 BSEP 12-0090, Technical Specification Bases, Brunswick Steam Electric Plant, Unit 2 - Renewed Facility Operating License DPR-62, Revision 762012-08-14014 August 2012 Technical Specification Bases, Brunswick Steam Electric Plant, Unit 2 - Renewed Facility Operating License DPR-62, Revision 76 ML11270A3712011-12-21021 December 2011 Issuance of Amendments Regarding Adoption of TSTF-514 BSEP 10-0057, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report2010-04-29029 April 2010 Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report BSEP 10-0052, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report2010-04-29029 April 2010 Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report BSEP 08-0145, Renewed Facility Operating License, Technical Specification Bases, Revision 572008-10-30030 October 2008 Renewed Facility Operating License, Technical Specification Bases, Revision 57 ML0832204692008-10-30030 October 2008 Renewed Facility Operating License, Technical Specification Bases, Revision 60 ML0828301372008-10-0606 October 2008 License Amendment Request to Eliminate Work Hour Controls to Support Compliance with Revised 10 CFR 26 BSEP 08-0082, Request for License Amendment - Adoption of TSTF-475, Revision 1 - Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2008-06-19019 June 2008 Request for License Amendment - Adoption of TSTF-475, Revision 1 - Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process ML0727101412007-09-27027 September 2007 Tech Spec Pages for Amendments 242 and 270 Related to Main Fuel Oil Storage Tank BSEP 07-0082, Submittal of Technical Specification Bases Revisions2007-08-14014 August 2007 Submittal of Technical Specification Bases Revisions BSEP 07-0080, Request for License Amendment Re Technical Specification 3.3.1.2, Source Range Monitor (SRM) Instrumentation.2007-08-13013 August 2007 Request for License Amendment Re Technical Specification 3.3.1.2, Source Range Monitor (SRM) Instrumentation. BSEP-07-0064, Request for License Amendments, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program2007-08-0606 August 2007 Request for License Amendments, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program BSEP 07-0058, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-07-17017 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process BSEP 07-0048, Submittal of Technical Specification Bases Revisions2007-05-28028 May 2007 Submittal of Technical Specification Bases Revisions BSEP 06-0129, Request for License Amendments Regarding Linear Heat Generation Rate and Core Operating Limits Report References for Areva Np Fuel2007-01-22022 January 2007 Request for License Amendments Regarding Linear Heat Generation Rate and Core Operating Limits Report References for Areva Np Fuel BSEP 06-0101, Submittal of Technical Specification Bases Revisions2006-09-14014 September 2006 Submittal of Technical Specification Bases Revisions BSEP 06-0044, Submittal of Technical Specification Bases Revisions2006-04-13013 April 2006 Submittal of Technical Specification Bases Revisions BSEP 05-0109, Submittal of Technical Specification Bases Revisions2005-08-16016 August 2005 Submittal of Technical Specification Bases Revisions BSEP 05-0102, Request for License Amendment Revised Main Steam Isolation Valve Leakage Limit2005-08-11011 August 2005 Request for License Amendment Revised Main Steam Isolation Valve Leakage Limit BSEP 05-0094, Request for License Amendments - Appendix J Leakage Rate Testing Instrumentation Accuracy, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program2005-08-11011 August 2005 Request for License Amendments - Appendix J Leakage Rate Testing Instrumentation Accuracy, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program ML0518001622005-06-28028 June 2005 Technical Specification Page 3.4-10 RCS Ld Instrumentation (Tac No. MC7216, MC7217) ML0518001552005-06-28028 June 2005 Technical Specification Page 3.4-10 Re RCS Ld Instrumentation (Tac No. MC7216, MC7217) BSEP 05-0082, Submittal of Technical Specification Bases Changes2005-06-22022 June 2005 Submittal of Technical Specification Bases Changes 2023-02-16
[Table view] Category:Bases Change
MONTHYEARRA-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-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-21-0272, Supplement to 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 4b2021-11-0101 November 2021 Supplement to 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-18-0183, 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 4b2021-04-0101 April 2021 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-19-0431, Application to Revise Technical Specifications to Adopt TSTF 564, Safety Limit MCPR2020-03-0909 March 2020 Application to Revise Technical Specifications to Adopt TSTF 564, Safety Limit MCPR RA-19-0157, Supplement to Request for License Amendment Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time2019-03-26026 March 2019 Supplement to Request for License Amendment Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time RA-18-0079, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-08-14014 August 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO BSEP 18-0013, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-01-23023 January 2018 Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process BSEP 16-0067, Technical Specification Bases, Rev 882016-08-0303 August 2016 Technical Specification Bases, Rev 88 ML16224A2832016-08-0303 August 2016 Technical Specification Bases, Rev 88 BSEP 16-0047, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program2016-06-29029 June 2016 Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016 Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process ML15175A4472015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6 ML15175A4482015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6 ML15175A4452015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6 ML15175A4422015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 3 of 6 RA-15-0006, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 62015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 6 BSEP 12-0090, Technical Specification Bases, Brunswick Steam Electric Plant, Unit 2 - Renewed Facility Operating License DPR-62, Revision 762012-08-14014 August 2012 Technical Specification Bases, Brunswick Steam Electric Plant, Unit 2 - Renewed Facility Operating License DPR-62, Revision 76 ML12237A0532012-08-14014 August 2012 Technical Specification Bases, Brunswick Steam Electric Plant, Unit 1 - Renewed Facility Operating License DPR-71, Revision 80 BSEP 08-0145, Renewed Facility Operating License, Technical Specification Bases, Revision 572008-10-30030 October 2008 Renewed Facility Operating License, Technical Specification Bases, Revision 57 ML0832204692008-10-30030 October 2008 Renewed Facility Operating License, Technical Specification Bases, Revision 60 BSEP 07-0082, Submittal of Technical Specification Bases Revisions2007-08-14014 August 2007 Submittal of Technical Specification Bases Revisions BSEP 07-0058, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-07-17017 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process BSEP 07-0048, Submittal of Technical Specification Bases Revisions2007-05-28028 May 2007 Submittal of Technical Specification Bases Revisions BSEP 06-0129, Request for License Amendments Regarding Linear Heat Generation Rate and Core Operating Limits Report References for Areva Np Fuel2007-01-22022 January 2007 Request for License Amendments Regarding Linear Heat Generation Rate and Core Operating Limits Report References for Areva Np Fuel BSEP 06-0101, Submittal of Technical Specification Bases Revisions2006-09-14014 September 2006 Submittal of Technical Specification Bases Revisions BSEP 06-0044, Submittal of Technical Specification Bases Revisions2006-04-13013 April 2006 Submittal of Technical Specification Bases Revisions BSEP 05-0109, Submittal of Technical Specification Bases Revisions2005-08-16016 August 2005 Submittal of Technical Specification Bases Revisions BSEP 05-0082, Submittal of Technical Specification Bases Changes2005-06-22022 June 2005 Submittal of Technical Specification Bases Changes BSEP 05-0043, Submittal of Technical Specification Bases Change2005-03-24024 March 2005 Submittal of Technical Specification Bases Change BSEP 05-0008, Request for License Amendments - Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency, Consolidated Line Item Improvement Process (TSTF-460)2005-01-27027 January 2005 Request for License Amendments - Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency, Consolidated Line Item Improvement Process (TSTF-460) BSEP 05-0012, Submittal of Technical Specification Bases Changes2005-01-26026 January 2005 Submittal of Technical Specification Bases Changes BSEP 04-0160, Submittal of Technical Specification Bases Change2004-12-10010 December 2004 Submittal of Technical Specification Bases Change BSEP 04-0134, Submittal of Technical Specification Bases Changes2004-09-16016 September 2004 Submittal of Technical Specification Bases Changes BSEP 04-0065, Units, 1 and 2 - Submittal of Technical Specification Bases Changes2004-06-0404 June 2004 Units, 1 and 2 - Submittal of Technical Specification Bases Changes BSEP 04-0046, Submittal of Technical Specification Bases Changes2004-03-29029 March 2004 Submittal of Technical Specification Bases Changes BSEP 04-0008, Submittal of Technical Specification Bases Change2004-01-12012 January 2004 Submittal of Technical Specification Bases Change ML0330803002003-10-23023 October 2003 Technical Specification Bases, Revision 30 ML0330802802003-10-23023 October 2003 Technical Specification Bases, Revision 31 BSEP-03-0126, Submittal of TS Bases Changes for Revision 30 & 292003-08-20020 August 2003 Submittal of TS Bases Changes for Revision 30 & 29 BSEP 03-0054, Submittal of Technical Specification Bases Changes Revisions 27 & 282003-03-28028 March 2003 Submittal of Technical Specification Bases Changes Revisions 27 & 28 BSEP 02-0177, Submittal of Technical Specification Bases Changes for Revisions 28 (Unit 1) & 25 (Unit 2)2002-10-25025 October 2002 Submittal of Technical Specification Bases Changes for Revisions 28 (Unit 1) & 25 (Unit 2) BSEP 02-0158, Submittal of Technical Specification Bases Changes for Revisions 272002-09-20020 September 2002 Submittal of Technical Specification Bases Changes for Revisions 27 BSEP 02-0114, Submittal of Technical Specification Bases Changes Revisions 24 & 252002-06-0505 June 2002 Submittal of Technical Specification Bases Changes Revisions 24 & 25 BSEP 02-0093, Part 2 of 2 - Brunswick, Units 1 and 2 - Submittal of Technical Specification Bases Changes for Revisions 21 and 22 (Units 1 and 2) and Revision 23 (Unit 1 Only)2002-05-0808 May 2002 Part 2 of 2 - Brunswick, Units 1 and 2 - Submittal of Technical Specification Bases Changes for Revisions 21 and 22 (Units 1 and 2) and Revision 23 (Unit 1 Only) BSEP 02-0047, Submittal of Technical Specification Bases Changes for Revision 202002-02-20020 February 2002 Submittal of Technical Specification Bases Changes for Revision 20 2023-02-16
[Table view] |
Text
a Progress Energy AMli 0 2003 BSEP03-0126 U Nuclear Regulatory Commission
~u/T VTTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 SUBMITTAL OF TECHNICAL SPECIFICATION BASES CHANGES FOR REVISION 30 (UNIT 1) AND 29 (UNTI 2)
Ladies and Gentlemen:
In accordance with Technical Specification (S) 5.5.10 for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2, Progress Energy Carolinas, Inc. is submitting Revisions 30 and 29 to the BSEP, Unit 1 and 2 TS Bases, respectively. Revisions 30 and 29 were implemented on August 6, 2003.
Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Supervisor -
Licensing/Regulatory Programs, at (910)457-2073.
Sincerely, Edward T. ONeil Manager - Support Services Brunswick Steam Electric Plant WRM/wrm
Enclosures:
- 1. Summary of Revisions to Technical Specification Bases
- 2. Page Replacement Instructions
- 3. Replacement Technical Specification Bases Pages Progress Energy Carolinas, Inc.
Brunswick Nuclear Plant -/
AoO(
P.O. Box 10429 Southport, NC 28461
Document Control Desk BSEP 03-0126 Page 2 cc (with enclosures):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Eugene M. DiPaolo, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATITN: Ms. Brenda L Mozafari (Mail Stop OWFN 8G9) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 Ms. Beverly 0. Hall, Section Chief Radiation Protection Section, Division of Radiation Protection North Carolina Department of Environment and Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7221
- a =
BSEP 03-0126 Enclosure 1 Page 1 of I Summary of Revisions to Technical Specification Bases Affected Date Revision Units Implemented Title/Description 30 Unit 1 August 6, 2003
Title:
Issuance of Amendment Regarding 29 Unit 2 Pressure/Temperature Limit Curves
Description:
Revisions 30 and 29 incorporate the bases changes associated with Facility Operating license Amendments 228 (Unit 1) and 256 (Unit 2),
issued June 18, 2003 (ADAMS Accession Number ML031690683).
BSEP 03-0126 Enclosure 2 Page 1 of 2 Page Change Instructions Unit - Bases Boo 0 Remove j Insert Title Page - Revision 29 Tide Page - Revision 30 LOEP-1, Revision 29 0 LOEP-1, Revision 30 I ...H
, .. ..., . .. I, II I I..I..I....................-....... . .- ,~
Remove Insert LOEP-1, Revision 29 LOEP-1, Revision 30 B 3.4-39, Revision 17 B 3.4-39, Revision 30 B 3.4-40, Revision 17 B 3.4-40, Revision 30 B 3.4-41, Revision 17 B 3.441, Revision 30 B 3.4-44, Revision 17 B 3.4-44, Revision 30 B 3.447, Revision 17 B 3.447, Revision 30
BSEP 03-0126 Enclosure 2 Page 2 of 2 Uni 2 ;-]ases Book1 Remove Insert Title Page - Revision 28 J Title Page - Revision 29 LOEP-1, Revision 28 LOEP-1, Revision 29 T--n t2 =B a s oo k -
Remove Insert LOEP-1, Revision 27 LOEP-1, Revision 29 LOEP-2, Revision 27 LOEP-2, Revision 29 B 3.4-39, Revision 17 B 3.4-39, Revision 29 B 3.4-40, Revision 17 B 3.4-40, Revision 29 B 3.4-41, Revision 17 B 3.4-41, Revision 29 B 3.4-44, Revision 17 B 3.4-44, Revision 29 B 3.447, Revision 17 B 3.4-47, Revision 29 B 3.6-66, Revision 27 B 3.6-66, Revision 29 B 3.6-67, Revision 18 B 3.6-67, Revision 29 B 3.6-71, Revision 21 B 3.6-71, Revision 29
- 6 BSEP 03-0126 Enclosure 3
- Replacement Technical Specification Bases Pages Revisions 30 (Unit 1) and 29 (Unit 2)
Vf -
Unit 1 Bases Book I Replacement Pages
- s BASES TO THE FACILITY OPERATING LICENSE DPR-71 TECHNICAL SPECIFICATIONS FOR BRUNSWICK STEAM ELECTRIC PLANT UNIT I CAROLINA POWER & LIGHT COMPANY REVISION 30
LIST OF EFFECTIVE PAGES - BASES Page No. Revision No. Page No. Revision No.
Title Page 30 B 3.1-7 0 I B 3.1-8 0 List of Effective Pages - Book I B 3.1-9 0 B 3.1-10 0 LOEP-1 30 B 3.1-11 0 I LOEP-2 25 B 3.1-12 0 LOEP-3 24 B 3.1-13 0 LOEP-4 27 B 3.1-14 0 B 3.1-15 0 i 21 B 3.1-16 0 ii 21 B 3.1-17 25 B 3.1-18 25 B 2.0-1 0 B 3.1-19 0 B 2.0-2 0 B 3.1-20 0 B 2.0-3 25 B 3.1-21 0 B 2.0-4 24 B 3.1-22 0 B 2.0-5 24 B 3.1-23 0 B 2.0-6 24 B 3.1-24 23 B 2.0-7 24 B 3.1-25 0 B 2.0-8 0 B 3.1-26 23 B 3.1-27 23 B 3.0-1 0 B 3.1-28 0 B 3.0-2 0 B 3.1-29 0 B 3.0-3 0 B 3.1-30 0 B 3.0-4 0 B 3.1-31 0 B 3.0-5 0 B 3.1-32 0 B 3.0-6 0 B 3.1-33 25 B 3.0-7 0 B 3.1-34 25 B 3.0-8 0 B 3.1-35 25 B 3.0-9 0 B 3.1-36 25 B 3.0-10 0 B 3.1-37 24 B 3.0-11 0 B 3.1-38 24 B 3.0-12 0 B 3.1-39 24 B 3.0-13 28 B 3.1-40 24 B 3.0-14 28 B 3.1-41 24 B 3.0-15 28 B 3.1-42 24 B 3.0-16 28 B 3.1-43 24 B 3.1-44 24 B 3.1-1 0 B 3.1-45 0 B 3.1-2 0 B 3.1-46 0 B 3.1-3 0 B 3.1-47 0 B 3.1-4 0 B 3.1-48 24 B 3.1-5 0 B 3.1-6 0 (continued)
Brunswick Unit I LOEP-1I Revision 30 1
Unit 1 Bases Book 2 Replacement Pages
LIST OF EFFECTIVE PAGES - BASES Page No. Revision No. Page No. Revision No.
List of Effective Pages - Book 2 B 3.4-33 0 B 3.4-34 0 LOEP-1 30 B 3.4-35 0 I LOEP-2 26 B 3.4-36 0 LOEP-3 25 B 3.4-37 0 LOEP-4 29 B 3.4-38 0 LOEP-5 25 B 3.4-39 30 B 3.4-40 30 i 18 B 3.4-41 30 Ii 7 B 3.4-42 17 B 3.4-43 17 B 3.4-1 0 B 3.4-44 30 I B 3.4-2 0 B 3.4-45 17 B 3.4-3 25 B 3.4-46 17 B 3.4-4 21 B 3.4-47 30 I B 3.4-5 1 B 3.4-48 0 B 3.4-6 21 B 3.4-49 0 B 3.4-7 0 B 3.4-8 0 B 3.5-1 B 3.4-9 0 B 3.5-2 B 3.4-10 0 B 3.5-3 B 3.4-11 0 B 3.5-4 B 3.4-12 0 B 3.5-5 B 3.4-13 0 B 3.5-6 B 3.4-14 9 B 3.5-7 B 3.4-15 0 B 3.5-8 B 3.4-16 0 B 3.5-9 B 3.4-17 0 B 3.5-10 B 3.4-18 0 B 3.5-11 B 3.4-19 0 B 3.5-12 B 3.4-20 19 B 3.5-13 B 3.4-21 19 B 3.5-14 B 3.4-22 19 B 3.5-15 B 3.4-23 19 B 3.5-16 B 3.4-24 19 B 3.5-17 B 3.4-25 24 B 3.5-18 B 3.4-26 24 B 3.5-19 B 3.4-27 24 B 3.5-20 B 3.4-28 24 B 3.5-21 B 3.4-29 0 B 3.5-22 B 3.4-30 0 B 3.5-23 B 3.4-31 0 B 3.5-24 B 3.4-32 0 B 3.5-25 (continued)
Brunswick Unit 1 LOEP-1I Revision 30 1
RCS P/T Limits B 3.4.9 B 3.4 REACTOR COOLANT SYSTEM (RCS)
B 3.4.9 RCS Pressure and Temperature (P/T) Limits BASES BACKGROUND All components of the RCS are designed to withstand effects of cyclic loads due to system pressure and temperature changes. These loads are introduced by startup (heatup) and shutdown (cooldown) operations, power transients, and reactor trips. This LCO limits the pressure and temperature changes during RCS heatup and cooldown, within the design assumptions and the stress limits for cyclic operation.
This Specification-contains P/T limit curves for heatup, cooldown, and nservice leakage and hydrostatic testing, and data for the maximum rate of change of reactor coolant temperature. The criticality curve provides limits for both heatup and cooldown during criticality. Development of the curves considered instrument uncertainty values of 1oaF for temperature and 15 psig for pressure plus an additional 15 psig for pressure instrument location (Ref. ).
Each P/T limit curve defines an acceptable region for normal operation. The usual use of the curves is operational guidance during heatup or cooldown maneuvering, when pressure and temperature indications are monitored and compared to the applicable curve to determine that operation is within the allowable region.
The LCO establishes operating limits that provide a margin to brittle failure of the reactor vessel and piping of the reactor coolant pressure boundary (RCPB). The vessel (including its appurtenances) is the component most subject to brittle failure. Therefore, the LCO limits apply mainly to the vessel (including its appurtenances).
10 CFR 50, Appendix G (Ref. 2), requires the establishment of P/T limits for material fracture toughness requirements of the RCPB materials. Reference 2 requires an adequate margin to brittle failure during normal operation, anticipated operational occurrences, and system hydrostatic tests. It mandates the use of the ASME Code,Section XI, Appendix G (Ref. 3).
(continued)
Brunswick Unit 8 3.4-39 Revision No. 30 1
RCS P/T Limits B 3.4.9 BASES BACKGROUND The P/T limit curves in this Specification were developed in (continued) accordance with the 1989 Edition of the ASME Code,Section XI, Appendix G (Ref. 3). These P/T limit curves were developed using the initiation fracture toughness, K for the allowable material fracture toughness. The use or K for development of P/T limit curves has been approved by the ASME through Code Case N-640 (Ref. 4).
The actual shift in the RTDT of the vessel material will be established periodically by removing and evaluating the irradiated reactor vessel material specimens, in accordance with the UFSAR (Ref. 5) and Appendix H of 10 CFR 50 (Ref. 6). The operating P/T limit curves will be adjusted, as necessary, based on the evaluation findings and the recommendations of Reference 7.
The bounding P/T limit curves are based on the N16 instrumentation nozzles. These nozzles are located at the top of the beltline region and were determined to be the limiting material with respect to the P/T curves.
The heatup curve represents a different set of restrictions than the cooldown curve because the directions of the thermal gradients through the vessel wall are reversed. The thermal gradient reversal alters the location of the tensile stress between the outer and Inner walls.
The criticality limits include the Reference 2 requirement that they be at least 40F above the noncritical heatup curve or the cooldown curve and not lower than the minimum permissible temperature for the inservice leakage and hydrostatic testing.
The consequence of violating the LCO limits is that the RCS has been operated under conditions that can result in brittle failure of the RCPB, possibly leading to a nonisolable leak or loss of coolant accident. In the event these limits are exceeded, an evaluation must be performed to determine the effect on the structural integrity of the RCPB components. ASME Code,Section XI, Appendix E (Ref. 8), provides a recommended methodology for evaluating an operating event that causes an excursion outside the limits.
(continued)
Brunswick Unit 8 3.4-40 Revision No. 30 1
RCS P/T Limits B 3.4.9 BASES (continued)
APPLICABLE The P/T limits are not derived from Design Basis Accident SAFETY ANALYSES (DBA) analyses. They are prescribed during normal operation to avoid encountering pressure, temperature, and temperature rate of change conditions that might cause undetected flaws to propagate and cause nonductile failure of the RCPB, a condition that is unanalyzed. Reference 9 provides the curves and limits in this Specification. Since the P/T limits are not derived from any DBA, there are no acceptance limits related to the P/T limits. Rather, the P/T limits are acceptance limits themselves since they preclude operation in an unanalyzed condition.
RCS P/T limits satisfy Criterion 2 of 10 CFR 50.36(c)(2)(ii)
(Ref. 10).
LCO The elements of this LCO are:
- a. RCS pressure and temperature are within the applicable limits specified in Figures 3.4.9-1 and 3.4.9-2, and heatup or cooldown rates are 100 F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, during RCS heatup and cooldown;
- b. RCS pressure and temperature are within the applicable limits in Figure 3.4.9-3, 3.4.9-4, or 3.4.9-5 and I heatup or cooldown rates are < 30F in any I hour period, during RCS inservice leak and hydrostatic testing;
- c. The temperature difference between the reactor vessel bottom head coolant and the reactor pressure vessel (RPV) coolant is s 145*F during recirculation pump startup;
- d. The temperature difference between the reactor coolant in the respective recirculation loop and in the reactor vessel is 5 50F during recirculation pump startup;
- e. RCS pressure and temperature are within the criticality limits specified in Figure 3.4.9-2, prior to achieving criticality; and
- f. The reactor vessel flange and the head flange temperatures are 2 70F when tensioning the reactor vessel head bolting studs.
(continued)
Brunswick Unit B 3.4-41 Revision No. 30 1
RCS P/T Limits B 3.4.9 BASES ACTIONS B.1 and B.2 (continued)
Pressure and temperature are reduced by placing the plant in at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
C.1 and C.2 Operation outside the P/T limits in other than MODES 1, 2, and 3 (including defueled conditions) must be corrected so that the RCPB is returned to a condition that has been verified as safe by stress analyses. The Required Action must be initiated without delay and continued until the limits are restored. With the applicable limits of Figures 3.4.9-3, 3.4.9-4, or 3.4.9-5 exceeded during inservice hydrostatic and leak testing operations, the maximum temperature-change shall be limited to 10*F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period during restoration of the PT limit parameters to within limits.
Besides restoring the PT limit parameters to within limits, an engineering evaluation is required to determine if RCS operation is allowed. This'engineering evaluation will determine the effect of the P/T limit violation on the fracture toughness properties of the RCS. This evaluation must verify that the RCPB integrity is acceptable and must be completed before approaching criticality or heating up to
> 212F. Several methods may be used, including comparison with pre-analyzed transients, new analyses, or inspection of the components. ASME Code,Section XI, Appendix E (Ref. 8),
may be used to support the evaluation; however, its use is restricted to evaluation of the beltline.
Condition C is modified by a Note requiring Required Action C.2 to be completed whenever the Condition is entered. The Note emphasizes the need to perform the evaluation of the effects of the excursion outside the allowable limits. Restoration alone per Required Action C.1 is insufficient because higher than analyzed stresses may have occurred and may have affected the RCPB integrity.
(continued)
Brunswick Unit 8 3.4-44 Revision No. 30 1
RCS P/T Limits B 3.4.9 BASES SURVEILLANCE SR 3.4.9.6. SR 3.4.9.7. and SR 3.4.9.8 (continued)
REQUIREMENTS The 30 minute Frequency reflects the urgency of maintaining the temperatures within limits, and also limits the time that the temperature limits could be exceeded. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is reasonable based on the rate of temperature change possible at these temperatures.
SR 3.4.9.6 is modified by a Note that requires the Surveillance to be performed only when tensioning the reactor vessel head bolting studs. SR 3.4.9.7 is modified by a Note that requires the Surveillance to be initiated 30 minutes after RCS temperature is < 80F in MODE 4.
SR 3.4.9.8 is modified by a Note that requires the Surveillance to be initiated 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after RCS temperature is < 100*F in MODE 4. The Notes contained in these SRs are necessary to specify when the reactor vessel flange and head flange temperatures are required to be verified to be within the specified limits.
REFERENCES 1. Calculation B21-1029, "Instrument Uncertainty for RCS Pressure/Temperature Limits Curve," Revision 0.
- 2. 10 CFR 50, Appendix G.
- 3. 1989 Edition of the ASME Code,Section XI, Appendix G.
- 4. ASME Code Case N-640. Alternate References Fracture Toughness for Development of P-T Limit CurvesSection XI. Division 1."
- 5. UFSAR, Section 5.3.1.6 and Appendix 5.3B.
- 6. 10 CFR 50, Appendix H.
- 7. Regulatory Guide 1.99, Revision 2, May 1988.
- 8. ASME, Boiler and Pressure Vessel Code,Section XI, Appendix E.
- 9. Calculation OB11-0005, Development of RPV Pressure-Temperature Curves For BNP Units I and 2 For Up To 32 EFPY of Plant Operation," Revision 1.
- 10. 10 CFR 50.36(c)(2)(ii).
Brunswick Unit B 3.4-47 Revision No. 30 1
- Unit 2 Bases Book 1 Replacement Pages
BASES TO THE FACILITY OPERATING LICENSE DPR-62 TECHNICAL SPECIFICATIONS FOR BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 CAROLINA POWER & LIGHT COMPANY REVISION 29
LIST OF EFFECTIVE PAGES - BASES paae No. Revision No. Page No. Revision No.
Title Page 29 B 3.1-7 0 I B 3.1-8 0 List of Effective Pages - Book 1 B 3.1-9 0 B 3.1-10 0 LOEP-1 29 B 3.1-11 0 I LOEP-2 27 B 3.1-12 0 LOEP-3 27 B 3.1-13 0 LOEP-4 27 B 3.1-14 0 B 3.1-15 0 27 B 3.1-16 0 ii 27 27 B 3.1-17 B 3.1-18 27 B 2.0-1 0 B 3.1-19 0 B 2.0-2 0 B 3.1-20 0 B 2.0-3 27 B 3.1-21 0 B 2.0-4 27 B 3.1-22 0 B 2.0-5 27 B 3.1-23 0 B 2.0-6 27 B 3.1-24 22 B 2.0-7 27 B 3.1-25 0 B 2.0-8 0 B 3.1-26 22 B 3.1-27 22 B 3.0-1 0 B 3.1-28 0 B 3.0-2 0 B 3.1-29 0 B 3.0-3 0 B 3.1-30 0 B 3.0-4 0 B 3.1-31 0 B 3.0-5 0 B 3.1-32 0 B 3.0-6 0 B 3.1-33 27 B 3.0-7 0 B 3.1-34 27 B 3.0-8 0 B 3.1-35 27 B 3.0-9 0 B 3.1-36 27 B 3.0-10 0 B 3.1-37 21 B 3.0-11 0 B 3.1-38 28 B 3.0-12 0 B 3.1-39 28 B 3.0-13 25 B 3.1-40 27 B 3.0-14 25 B 3.1-41 27 B 3.0-15 25 B 3.1-42 27 B 3.0-16 25 B 3.1-43 28 B 3.1-44 27 B 3.1-1 0 B 3.1-45 0 B 3.1-2 0 B 3.1-46 0 B 3.1-3 0 B 3.1-47 0 B 3.1-4 0 8 3.1-48 27 B 3.1-5 0 B 3.1-6 0 (continued)
Brunswick Unit 2 LOEP-1 Revision 29 1
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Unit 2 Bases Book 2 Replacement Pages
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Brunswick Unit 2 LOEP-1 Revision 29 1
LIST OF EFFECTIVE PAGES - BASES (continued)
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Brunswick Unit 2 LOEP-2 Revision 29 1
RCS P/T Limits B 3.4.9 B 3.4 REACTOR COOLANT SYSTEM (RCS)
B 3.4.9 RCS Pressure and Temperature (P/T) Limits BASES BACKGROUND All components of the RCS are designed to withstand effects of cyclic loads due to system pressure and temperature changes. These loads are introduced by startup (heatup) and shutdown (cooldown) operations, power transients, and reactor trips. This LCO limits the pressure and temperature changes during RCS heatup and cooldown, within the design assumptions and the stress limits for cyclic operation.
This Specification contains P/T limit curves for heatup, cooldown, and inservice leakage and hydrostatic testing, and data for the maximum rate of change of reactor coolant temperature. The criticality curve provides limits for both heatup and cooldown during criticality. Development of the curves considered instrument uncertainty values of 1O*F for temperature and 15 psig for pressure plus an additional 15 psig for pressure instrument location (Ref. 1).
Each P/T limit curve defines an acceptable region for normal operation. The usual use of the curves is operational guidance during heatup or cooldown maneuvering, when pressure and temperature indications are monitored and compared to the applicable curve to determine that operation is within the allowable region.
The LCO establishes operating limits that provide a margin to brittle failure of the reactor vessel and piping of the reactor coolant pressure boundary (RCPB). The vessel (including its appurtenances) is the component most subject to brittle failure. Therefore, the UCO limits apply mainly to the vessel (including its appurtenances).
10 CFR 50, Appendix G (Ref. 2), requires the establishment of P/T limits for material fracture toughness requirements of the RCPB materials. Reference 2 requires an adequate margin to brittle failure during normal operation, anticipated operational occurrences, and system hydrostatic tests. It mandates the use of the ASME Code,Section XI, Appendix G (Ref. 3).
(continued)
Brunswick Unit 2 IB 3.4-39 Revision No. 29 1
RCS P/T Limits B 3.4.9 BASES BACKGROUND The P/T limit curves in this Specification were developed in accordance with the 1989 Edition of the ASME Code,Section XI, Appendix G (Ref. 3). These P/T limit curves were developed using the initiation fracture toughness, K for the allowable material fracture toughness. The use of K for development of P/T limit curves has been approved by tIe ASME through Code Case N-640 (Ref. 4).
The actual shift in the RTDT of the vessel material will be established periodically by removing and evaluating the irradiated reactor vessel material specimens, in accordance with the UFSAR Ref. 5) and Appendix H of 10 CFR 50 (Ref. 6). The operating P/T limit curves will be adjusted, as necessary, based on the evaluation findings and the recommendations of Reference 7.
The bounding P/T limit curves are based on the N16 instrumentation nozzles. These nozzles are located at the top of the beltline region and were determined to be the limiting material with respect to the P/T curves.
The heatup curve represents a different set of restrictions than the cooldown curve because the directions of the thermal gradients through the vessel wall are reversed. The thermal gradient reversal alters the location of the tensile stress between the outer and inner walls.
The criticality limits include the Reference 2 requirement that they be at least 40F above the noncritical heatup curve or the cooldown curve and not lower than the minimum permissible temperature for the inservice leakage and hydrostatic testing.
The consequence of violating the LCO limits is that the RCS has been operated under conditions that-can result in brittle failure of the RCPB, possibly leading to a nonisolable leak or loss of coolant accident. In the event these limits are exceeded, an evaluation must be performed to determine the effect on the structural integrity of the RCPB components. ASME Code,Section XI, Appendix E (Ref. 8), provides a recommended methodology for evaluating an operating event that causes an excursion outside the limits.
(continued Brunswick Unit 2 B 3.4-40 Revision No. 29 1
RCS P/T Limits B 3.4.9 BASES (continued APPLICABLE The P/T limits are not derived from Design Basis Accident SAFETY ANALYSES (DBA) analyses. They are prescribed during normal operation to avoid encountering pressure, temperature, and temperature rate of change conditions that might cause undetected flaws to propagate and cause nonductile failure of the RCPB, a condition that is unanalyzed. Reference 9 provides the curves and limits in this Specification. Since the P/T limits are not derived from any DBA, there are no acceptance limits related to the P/T limits. Rather, the P/T limits are acceptance limits themselves since they preclude operation in an unanalyzed condition.
RCS P/T limits satisfy Criterion 2 of 10 CFR 50.36(c)(2)(ii)
(Ref. 10).
LCO The elements of this LCO are:
- a. RCS pressure and temperature are within the applicable limits specified in Figures 3.4.9-1 and 3.4.9-2, and heatup or cooldown rates are c 100*F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, during RCS heatup and cooldown;
- b. RCS pressure and temperature are within the applicable limits in Figure 3.4.9-3, 3.4.9-4, or 3.4.9-5, and I heatup or cooldown rates are < 30F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, during RCS inservice leak and hydrostatic testing;
- c. The temperature difference between the reactor vessel bottom head coolant and the reactor pressure vessel (RPV) coolant is s 145*F during recirculation pump startup;
- d. The temperature difference between the reactor coolant in the respective recirculation loop and in the reactor vessel is c 50'F during recirculation pump startup;
- e. RCS pressure and temperature are within the criticality limits specified in Figure 3.4.9-2, prior to achieving criticality; and
- f. The reactor vessel flange and the head flange temperatures are 2 70F when tensioning the reactor vessel head bolting studs.
(continued)
Brunswick Unit 2 B 3.4-41 Revision No. 29 1
RCS P/T Limits B 3.4.9 BASES ACTIONS B.1 and B.2 (continued)
Pressure and temperature are reduced by placing the plant in at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
C.1 and C.2 Operation outside the P/T limits in other than MODES 1, 2, and 3 (including defueled conditions) must be corrected so that the RCPB is returned to a condition that has been verified as safe by stress analyses. The Required Action must be initiated without delay and continued until the limits are restored. With the applicable limits of Figures 3.4.9-3, 3.4.9-4, or 3.4.9-5 exceeded during inservice hydrostatic and leak testing operations, the maximum temperature change shall be limited to 10*F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period during restoration of the P/T limit parameters to within limits.
Besides restoring the P/T limit parameters to within limits, an engineering evaluation is required to determine if RCS operation is allowed. This engineering evaluation will determine the effect of the P/T limit violation on the fracture toughness properties of the RCS. This evaluation must verify that the RCPB Integrity is acceptable and must be completed before approaching criticality or heating up to
> 212-F. Several methods may be used, including comparison with pre-analyzed transients, new analyses, or inspection of the components. ASME Code,Section XI, Appendix E (Ref. 8),
may be used to support the evaluation; however, its use is restricted to evaluation of the beltline.
Condition C is modified by a Note requiring Required Action C.2 to be completed whenever the Condition is entered. The Note emphasizes the need to perform the evaluation of the effects of the excursion outside the allowable limits. Restoration alone per Required Action C.1 is insufficient because higher than analyzed stresses may have occurred and may have affected the RCPB integrity.
(continued)
Brunswick Unit 2 B 34-44 Revision No. 29 1
RCS P/T Limits B 3.4.9 BASES SURVEILLANCE SR 3.4.9.6. SR 3.4.9.7. and SR 3.4.9.8 (continued)
REQUI[REMENTS:
The 30 minute Frequency reflects the urgency of maintaining the temperatures within limits, and also limits the time that the temperature limits could be exceeded. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is reasonable based on the rate of temperature change possible at these temperatures.
SR 3.4.9.6 is modified by a Note that requires the Surveillance to be performed only when tensioning the reactor vessel head bolting studs. SR 3.4.9.7 is modified by a Note that requires the Surveillance to be initiated 30 minutes after RCS temperature is m 80OF in MODE 4.
SR 3.4.9.8 is modified by a Note that requires the Surveillance to be initiated 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after RCS temperature is 100OF in MODE 4. The Notes contained in these SRs are necessary to specify when the reactor vessel flange and head flange temperatures are required to be verified to be within the specified limits.
REFERENCES 1. Calculation OB21-1029, "Instrument Uncertainty for RCS Pressure/Temperature Limits Curve," Revision 0.
- 2. 10 CFR 50, Appendix G.
- 3. 1989 Edition of the ASME Code,Section XI, Appendix G.
- 4. ASME Code Case N640, "Alternative Reference Fracture Toughness for Development of P-T Limit CurvesSection XI, Division ."
- 5. UFSAR, Section 5.3.1.6 and Appendix 5.3B.
- 6. 10 CFR 50, Appendix H.
- 7. Regulatory Guide 1.99, Revision 2, May 1988.
- 8. ASME, Boiler and Pressure Vessel Code,Section XI, Appendix E.
- 9. Calculation OB11-0005, Development of RPV Pressure-Temperature Curves For BNP Units 1 and 2 For Up To 32 EFPY of Plant Operation," Revision 1.
- 10. 10 CFR 50.36(c)(2)(ii).
Brunswick Unit 2 B 3.4-47 Revision No. 0 1
CAD System B 3.6.3.2 BASES APPLICABILITY In MODE 3, both'the hydrogen and oxygen production rates and (continued) the total amounts produced after a LOCA would be less than those calculated for the Design Basis Accident LOCA. Thus, if the analysis were to be performed starting with a LOCA in MODE 3, the time to reach a flammable concentration would be extended beyond the time conservatively calculated for MODE 1. The extended time would allow hydrogen removal from the primary containment atmosphere by other means and also allow repair of an inoperable CAD subsystem, if CAD were not available. Therefore, the CAD System is not required to be OPERABLE in MODE 3.
In MODES 4 and 5, the probability and consequences of a LOCA are reduced due to the pressure and temperature limitations of these MODES. Therefore, the CAD System is not required to be OPERABLE in MODES 4 and 5.
ACTIONS A.I If the CAD System (one or both subsystems) is inoperable, it must be restored to OPERABLE status within 31 days. In this I Condition, the oxygen control function of the CAD System is lost. However, alternate oxygen control capabilities may be provided by the Containment Inerting System. 'The 31 day Completion Time is based on the low probability of the occurrence of a LOCA that would generate hydrogen and oxygen in amounts capable of exceeding the flammability limit, the amount of time available after the event for operator action to prevent exceeding this limit, and the availability of other hydrogen mitigating systems.
Required Action A.1 has been modified by a Note that indicates that the provisions of LCO 3.0.4 are not applicable. As a result, a MODE change is allowed when the CAD System (one or both subsystems) is inoperable. This allowance is provided because of the low probability of the occurrence of a LOCA that would generate hydrogen and oxygen in amounts capable of exceeding the flammability limit, the amount of time available after a postulated LOCA for operator action to prevent exceeding the flammability limit, and the availability of other hydrogen mitigating systems.
(continued)
Brunswick Unit 2 B 3.6-66 Revision No. 29 1
CAD System B 3.6.3.2 BASES z ~~~~~~~~~i L ACTIONS B.1 (continued)
If Required Action A.1 cannot be met within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 2 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
The allowed Completion Time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is reasonable, based on operating experience, to reach MODE 2 from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3.6.3.2.1 REQUIREMENTS Verifying that there is x 4350 gal of liquid nitrogen supply in the CAD System will ensure at least 29 days of post-LOCA CAD operation. This minimum volume of liquid nitrogen allows sufficient time after an accident to replenish the nitrogen supply for long term inerting. This is verified every 31 days to ensure that the system is capable of performing its intended function when required. The 31 day Frequency is based on operating experience, which has shown 31 days to be an acceptable period to verify the liquid nitrogen supply and on the availability of other hydrogen mitigating systems.
SR 3.6.3.2.2 Verifying the correct alignment for manual, power operated, and automatic valves in each of the CAD subsystem flow paths provides assurance that the proper flow paths exist for system operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since these valves were verified to be in the correct position prior to locking, sealing, or securing.
A valve is also allowed to be in the nonaccident position provided it can be aligned to the accident position within the time assumed in the accident analysis. This is acceptable because the CAD System is manually initiated.
This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of being mispositioned are in the correct position.
(continued)
Brunswick Unit 2 B 3.6-67 Revision No. 29 1
Secondary Containment B 3.6.4.1 BASES ACTIONS A.1 (continued) containment during MODES 1, 2, and 3. This time period also ensures that the probability of an accident (requiring secondary containment OPERABILITY) occurring during periods where secondary containment is inoperable is minimal.
B.1 and .2 If secondary containment cannot be restored to OPERABLE status within the required Completion Time, the plant must be brought to a MODE in which the CO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
C.1 and C.2 Movement of recently irradiated fuel assemblies in the secondary containment and OPDRVs can be postulated to cause significant fission product release to the secondary containment. In such cases, the secondary containment is the only barrier to release of fission products to the environment. Therefore, movement of recently irradiated fuel assemblies must be immediately suspended if the secondary containment is inoperable. Suspension of this activity shall not preclude completing an action that involves moving a component to a safe position. Also, action must be immediately initiated to suspend OPDRVs to minimize the probability of a vessel draindown and subsequent potential for fission product release. Actions must continue until OPDRVs are suspended.
LCO 3.0.3 is not applicable while in MODE 4 or 5. However, since recently irradiated fuel assembly movement can occur in MODE 1, 2, or 3, Required Action C.1 has been modified by a Note stating that LCO 3.0.3 is not applicable. If moving recently irradiated fuel assemblies while in MODE 4 or 5, LCO 3.0.3 would not specify any action. If moving recently irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations.
Therefore, in either case, inability to suspend movement (continued)
Brunswick Unit 2 B 3.6-71 Revision No. 29 1