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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:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRA-23-0122, License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to .2023-08-17017 August 2023 License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to . 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-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-21-0197, 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-21-0239, Application to Revise Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2021-12-0202 December 2021 Application to Revise Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling 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-21-0141, Units 1 & 2 - 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 Initiative2021-04-26026 April 2021 Units 1 & 2 - 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 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-21-0009, Request for License Amendment - Standby Liquid Control (SLC) System Boron Solution Storage Tank Volume2021-02-23023 February 2021 Request for License Amendment - Standby Liquid Control (SLC) System Boron Solution Storage Tank Volume RA-20-0361, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, Dated September 24, 2020, ADAMS Accession Number ML20272A0912020-11-17017 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, Dated September 24, 2020, ADAMS Accession Number ML20272A091 RA-20-0165, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-24024 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RA-20-0127, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22020-07-27027 July 2020 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 RA-20-0142, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems2020-07-21021 July 2020 Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems RA-19-0437, Nos. 1 & 2 - License Amendment Request to Modify Approved 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Categorization Process2020-07-0909 July 2020 Nos. 1 & 2 - License Amendment Request to Modify Approved 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Categorization Process 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 ML20073F1862020-03-0606 March 2020 Issuance of Amendment Nos. 299 and 327 to Revise Technical Specification 5.6.5b to Allow Application of Advanced Framatome Atrium 11 Fuel Methodologies (EPID L-2018-LLA-0273) (Redacted) 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-19-0139, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-03-18018 March 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0015, Request for License Amendment: Surveillance Requirements for Safety Relief Valves2019-03-0404 March 2019 Request for License Amendment: Surveillance Requirements for Safety Relief Valves RA-18-0148, License Amendment Request to Revise Units 1 and 2 Technical Specification 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2019-02-27027 February 2019 License Amendment Request to Revise Units 1 and 2 Technical Specification 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RA-18-0234, (Bsep), Unit Nos. 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-269, Allow Administrative Means of Position Verification for Locked or Sealed Valves.2018-12-14014 December 2018 (Bsep), Unit Nos. 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-269, Allow Administrative Means of Position Verification for Locked or Sealed Valves. ML18291A6282018-10-18018 October 2018 Request for License Amendment - Technical Specification 3.3.8.1, Loss of Power (LOP) Instrumentation RA-18-0135, Request for License Amendment - Technical Specification 3.7.4, Control Room Air Conditioning (AC) System2018-08-30030 August 2018 Request for License Amendment - Technical Specification 3.7.4, Control Room Air Conditioning (AC) System RA-18-0073, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D2018-06-28028 June 2018 Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D 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 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 17-0111, 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 17-0108, 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 17-0078, 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 17-0060, 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. ML17088A3962017-06-0707 June 2017 Issuance of Amendments Regarding Revisions of Technical Specifications to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs BSEP 17-0020, Supplement - License Amendment Request Regarding Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program2017-02-27027 February 2017 Supplement - License Amendment Request Regarding Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program BSEP 16-0083, Steam Electric Plant, Units 1 And. 2 - Application to Revise Technical Specifications to Adopt TSTF-535, Revision O, Revise Shutdown Margin Definition to Address Advance Fuel Designs.2016-11-18018 November 2016 Steam Electric Plant, Units 1 And. 2 - Application to Revise Technical Specifications to Adopt TSTF-535, Revision O, Revise Shutdown Margin Definition to Address Advance Fuel Designs. BSEP 16-0082, Transmittal of Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2016-10-27027 October 2016 Transmittal of Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. BSEP 16-0087, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A.2016-09-28028 September 2016 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A. 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 ML16287A4222016-09-26026 September 2016 FS1-0028339 Revision 1.0, Brunswick, Unit 1, Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM30 Methodology. BSEP 16-0078, Request for License Amendment - Revision to Technical Specification 2.1.1.2 Minimum Critical Power Ratio Safety Limit2016-09-26026 September 2016 Request for License Amendment - Revision to Technical Specification 2.1.1.2 Minimum Critical Power Ratio Safety Limit BSEP 16-0014, Request for License Amendment-Reactor Protection System(Rps) Electrical Protection Assembly (EPA) Electric Power Monitoring Surveillance Requirements (Srs) 3.3.8.2.2 and 3.3.8.2.32016-04-13013 April 2016 Request for License Amendment-Reactor Protection System(Rps) Electrical Protection Assembly (EPA) Electric Power Monitoring Surveillance Requirements (Srs) 3.3.8.2.2 and 3.3.8.2.3 RA-15-0040, License Amendment Request, Change in Corporate Form of Duke Energy Progress2016-02-0101 February 2016 License Amendment Request, Change in Corporate Form of Duke Energy Progress BSEP 15-0101, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program2015-12-21021 December 2015 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program 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 ML15175A4392015-06-24024 June 2015 Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-523, Rev. 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 1 of 6 RA-15-0009, Supplement to Application for Order Approving Transfer of Control of License and for Conforming License Amendment Pursuant to 10 CFR 50.80 and 10 CFR 50.902015-03-0404 March 2015 Supplement to Application for Order Approving Transfer of Control of License and for Conforming License Amendment Pursuant to 10 CFR 50.80 and 10 CFR 50.90 BSEP 15-0007, Request for License Amendments - Adoption of Topical Report ANP-10298P-A, Revision 12015-02-19019 February 2015 Request for License Amendments - Adoption of Topical Report ANP-10298P-A, Revision 1 2023-08-17
[Table view] Category:Technical Specifications
MONTHYEARML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML22082A2682022-05-0202 May 2022 Issuance of Amendment Nos. 308 and 336 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2 ML21067A2242021-04-30030 April 2021 Issuance of Amendment Nos. 305 and 333 to Revise License Conditions to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RA-21-0141, Units 1 & 2 - 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 Initiative2021-04-26026 April 2021 Units 1 & 2 - 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 ML20069J6312020-03-19019 March 2020 Correction to Amendment No. 304 Regarding Request to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program ML19346C7922020-02-0606 February 2020 Issuance of Amendments Nos. 298 and 326 to Modify Technical Specification to Extend Containment Leakage Test Intervals 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 17-0078, 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 ML17180A5962017-08-29029 August 2017 Issuance of Amendments to Adopt TSTF-423 Technical Specifications End States, NEDC-32988-A ML17130A7802017-07-12012 July 2017 Issuance of Amendments Regarding Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-545 ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML16019A0292016-02-0909 February 2016 Issuance of Amendments Regarding the Adoption of Topical Report ANP-10298P-A, Revision 1 ML15344A1532016-01-0808 January 2016 Issuance of Amendments Regarding Emergency Action Level Scheme Upgrade BSEP 15-0007, Request for License Amendments - Adoption of Topical Report ANP-10298P-A, Revision 12015-02-19019 February 2015 Request for License Amendments - Adoption of Topical Report ANP-10298P-A, Revision 1 ML12339A0672012-12-18018 December 2012 Issuance of License Amendments Regarding Cyber Security BSEP 12-0050, Request for License Amendments - Diesel Generator (DG) Completion Time (CT) Extension for Technical Specification (TS) 3.8.1, AC Sources - Operating2012-06-19019 June 2012 Request for License Amendments - Diesel Generator (DG) Completion Time (CT) Extension for Technical Specification (TS) 3.8.1, AC Sources - Operating BSEP 09-0019, Application to Revise Technical Specifications Regarding Primary Containment Isolation Instrumentation in Accordance with TSTF-306, Revision 22009-10-27027 October 2009 Application to Revise Technical Specifications Regarding Primary Containment Isolation Instrumentation in Accordance with TSTF-306, Revision 2 ML0923702842009-08-18018 August 2009 Units, 1 and 2, Request for License Amendments to Revise Local Power Range Monitor Calibration Frequency BSEP-09-0026, Request for License Amendment - Technical Specification 3.6.1.6, Suppression Chamber-to-Drywell Vacuum Breakers.2009-03-0909 March 2009 Request for License Amendment - Technical Specification 3.6.1.6, Suppression Chamber-to-Drywell Vacuum Breakers. BSEP 08-0156, Request for License Amendment - Adoption of TSTF-478, Revision 2 - BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control2008-11-24024 November 2008 Request for License Amendment - Adoption of TSTF-478, Revision 2 - BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control ML0817503332008-07-25025 July 2008 Technical Specifications, Adopted TSTF-448, Revision 3, Control Room Habitability (Tac Nos. MD6336 and MD6337) ML0819801252008-07-0909 July 2008 Submittal of Updated Technical Specifications Pages Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using Consolidated Line Item Improvement Process BSEP 08-0037, Progress Energy Carolinas' Submittal of Revision to Technical Specification 3.2.3, Linear Heat Generation Rate as Part of License Amendments for the Brunswick Steam Electric Plant Units 1 & 22008-03-0505 March 2008 Progress Energy Carolinas' Submittal of Revision to Technical Specification 3.2.3, Linear Heat Generation Rate as Part of License Amendments for the Brunswick Steam Electric Plant Units 1 & 2 BSEP 07-0139, Response to Request for Additional Information Regarding Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 32008-02-27027 February 2008 Response to Request for Additional Information Regarding Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3 ML0801800872008-02-0808 February 2008 Technical Specifications ML0801800952008-02-0808 February 2008 Technical Specifications ML0733203672007-11-27027 November 2007 Technical Specifications, Issuance of Amendment Storage of Areva Np Fuel BSEP 07-0081, Request for License Amendments to Revise Technical Specification 5.5.6, Inservice Testing Program, to Adopt Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-479, Revision 02007-09-26026 September 2007 Request for License Amendments to Revise Technical Specification 5.5.6, Inservice Testing Program, to Adopt Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-479, Revision 0 BSEP 07-0103, Supplement to Request for License Amendment Technical Specification 3.8.3, Diesel Fuel Oil, Provisions for Main Fuel Oil Storage Tank Inspection, Cleaning, or Repair2007-09-20020 September 2007 Supplement to Request for License Amendment Technical Specification 3.8.3, Diesel Fuel Oil, Provisions for Main Fuel Oil Storage Tank Inspection, Cleaning, or Repair 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 ML0704705612007-02-15015 February 2007 Tech Spec Pages for Amendments 241 and 269 to Adopt TSTF-372 BSEP 06-0136, Request for License Amendment, Technical Specification 3.4.1, Recirculation Loops Operating Recirculation Loop Operating Requirements.2006-12-21021 December 2006 Request for License Amendment, Technical Specification 3.4.1, Recirculation Loops Operating Recirculation Loop Operating Requirements. BSEP 06-0067, Request for License Amendment, Technical Specification 3.8.3, Diesel Fuel Oil, Provisions for Main Fuel Oil Storage Tank Inspection, Cleaning, or Repair2006-09-28028 September 2006 Request for License Amendment, Technical Specification 3.8.3, Diesel Fuel Oil, Provisions for Main Fuel Oil Storage Tank Inspection, Cleaning, or Repair ML0521703612005-08-0505 August 2005 Technical Specifications, Correct Omitted Page BSEP 05-0076, Submittal of Updated Technical Specification Pages, Technical Specification 3.4.5, RCS Leakage Detection Instrumentation2005-06-0909 June 2005 Submittal of Updated Technical Specification Pages, Technical Specification 3.4.5, RCS Leakage Detection Instrumentation ML0515403142005-05-31031 May 2005 Technical Specification Pages Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency ML0515403132005-05-31031 May 2005 Technical Specification Pages Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency ML0516800952005-05-23023 May 2005 E-mail Brunswick Cooling Tower Information BSEP 05-0060, Request for License Amendment Technical Specification 3.4.5, RCS Leakage Detection Instrumentation.2005-05-17017 May 2005 Request for License Amendment Technical Specification 3.4.5, RCS Leakage Detection Instrumentation. ML0506601502005-03-0404 March 2005 Technical Specification Pages, Amendment on Addition of Tracg Methodology for Determining Core Operating Limits (Tac No. MC4385) ML0503905032005-02-0202 February 2005 Tech Spec Pages for Amendment No. 261 Elimination of Requirements for Hydrogen and Oxygen Monitors Using the Consolidated Line Item Improvement Process ML0504002762005-02-0202 February 2005 Tech Spec Pages for Amendment No. 234 Elimination of Requirements for Hydrogen and Oxygen Monitors Using the Consolidated Line Item Improvement Process ML0501202082005-01-11011 January 2005 Technical Specifications, Increase Flexibility in Mode Restraints ML0501202112005-01-11011 January 2005 Technical Specifications, Increase Flexibility in Mode Restraints BSEP 04-0124, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2004-09-0303 September 2004 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process ML0408906732004-03-26026 March 2004 Technical Specification Pages 2.0-1 and 5.0-20, Amendment No. 231 Re. Minimum Critical Power Ratio Safety Limit ML0336001152003-12-19019 December 2003 Application for Technical Specification Change Re Mode Change Limitations Using Consolidated Line Item Improvement Process BSEP 03-0148, Request for License Amendment Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ration Safety Limits and Revision to References in Technical Specification 5.6.5, Core Operating Limits Report2003-10-31031 October 2003 Request for License Amendment Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ration Safety Limits and Revision to References in Technical Specification 5.6.5, Core Operating Limits Report BSEP-03-0003, Radioactive Effluent Release Report for 2002, Index, Section 6 Through Appendix H2003-04-28028 April 2003 Radioactive Effluent Release Report for 2002, Index, Section 6 Through Appendix H ML0308706642003-03-25025 March 2003 Technical Specification Page for Amendment 254 to License DPR-62, Revising Safety Limit Minimum Critical Power Ratio Values from 1.09 to 1.11 2023-08-29
[Table view] |
Text
James Scarola Vice President Brunswick Nuclear Plant Progress Energy Carolinas, Inc.
December 21, 2006 SERIAL: BSEP 06-0136 10 CFR 50.90 TSC-2006-04 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Docket Nos. 50-325 and 50-324/License Nos. DPR-71 and DPR-62 Request for License Amendment Technical Specification 3.4.1, "Recirculation Loops Operating" Recirculation Loop Operating Requirements Ladies and Gentlemen:
In accordance with the Code of Federal Regulations, Title 10, Part 50.90, Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc.,
is requesting a revision to the Technical Specifications (TSs) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The proposed license amendment revises TS 3.4.1, "Recirculation Loops Operating," to require the recirculation loops be operated with matched flows versus recirculation pump speeds as currently required. This change affects the Limiting Condition for Operation (LCO) requirements and Surveillance Requirements of TS 3.4.1. An evaluation of the proposed license amendment is provided in Enclosure 1.
CP&L has evaluated the proposed change in accordance with 10 CFR 50.91(a)(1), using the criteria in 10 CFR 50.92(c), and determined that this change involves no significant hazards considerations.
CP&L is providing, in accordance with 10 CFR 50.9 1(b), a copy of the proposed license amendment to the designated representative for the State of North Carolina.
CP&L requests approval of the proposed amendment by August 31, 2007, and that once approved, the amendment shall be implemented within 90 days.
No regulatory commitments are contained this submittal. Please refer any questions regarding this submittal to Mr. Randy C. Ivey, Manager - Support Services, at (910) 457-2447.
P.O.Box 10429 Southport, NC 28461 T> 910.457.3698 F> 910.457.2803
-A
Document Control Desk BSEP 06-0136 / Page 2 I declare, under penalty of perjury, that the foregoing is true and correct. Executed on December 21, 2006.
Sincerely, tJames Scarola MAT/mat
Enclosures:
- 1. Evaluation of License Amendment Request
- 2. Marked-up Technical Specification Pages - Unit 1
- 3. Typed Technical Specification Pages - Unit 1
- 4. Typed Technical Specification Pages - Unit 2
- 5. Marked-up Technical Specification Bases Pages - Unit 1 (For Information Only)
Document Control Desk BSEP 06-0136 / Page 3 cc (with enclosures):
U. S. Nuclear Regulatory Commission, Region II ATTN: Dr. William D. Travers, 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)
ATTN: 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 Environmental Health North Carolina Department of Environment and Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7221
BSEP 06-0136 Enclosure 1 Page 1 of 7 Evaluation of Proposed License Amendment Request
Subject:
Technical Specification 3.4.1, "Recirculation Loops Operating" Recirculation Loop Operating Requirements 1.0 Description This letter is a request to amend Renewed Operating Licenses DPR-71 and DPR-62 for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2.
The proposed change revises Technical Specification (TS) 3.4.1, "Recirculation Loops Operating," to require the recirculation loops be operated with matched flows versus recirculation pump speeds as currently required. During conversion of the BSEP TSs to the Improved Technical Specifications, as contained in Revision 1 of NUREG-1433, "Standard Technical Specifications General Electric Plants, BWR/4," a more restrictive change was made to require that operating recirculation loops be matched with respect to recirculation pump speeds. This deviated from the wording for Revision 1 of NUREG-1433, in that the NUREG required the loops be matched with respect to flows rather than pump speed. The Improved Technical Specifications were approved for BSEP Units 1 and 2 in Amendments 203 and 233, respectively, on June 5, 1998. Previous to conversion, the BSEP TSs required that two recirculation loops be in operation with no specific requirement for matching of flows or pump speeds. The change in nomenclature was made for operator convenience. Recirculation pump speed indication is readily available to the control room operators; whereas recirculation loop jet pump flow indication is not. As such, pump speed was chosen as the means to verify recirculation loop flow matching. Subsequently, it has been determined that pump speed requirements, established in Surveillance Requirement (SR) 3.4.1.1, are not sufficiently conservative. To remedy this condition, the Limiting Condition for Operation (LCO) requirements of TS 3.4.1 and SR 3.4.1.1 are being revised to require matched recirculation loop jet pump flow, consistent with NUREG-1433.
This condition was discovered on October 27, 2006, and is documented in Nuclear Condition Report 210701. Consistent with the guidance provided in Administrative Letter 98-10, "Disposition of Technical Specifications That Are Insufficient to Assure Plant Safety," dated December 29, 1998, administrative controls have been established to confirm recirculation loop jet pump flows are matched as well as complying with the existing SR 3.4.1.1 requirements.
Plant procedure OPT-13.5, "Reactor Recirculation Pump Differential Speed and Loop Flow Check," was issued, on October 27, 2006, to include the loop flow surveillance requirements.
2.0 Proposed Change The proposed change revises LCO 3.4.1 to require that two recirculation loops with matched flows be in operation. Currently, LCO 3.4.1 requires that the two recirculation loops have matched recirculation pump speeds. As a result of the revised LCO, SR 3.4.1.1 is being revised
BSEP 06-0136 Enclosure 1 Page 2 of 7 to require verification of matched recirculation loop jet pump flows. The specific wording of the proposed changes follows.
Existing Requirement Proposed Requirement LCO 3.4.1 Two recirculation loops with matched LCO 3.4.1 Two recirculation loops with matched recirculation pump speeds shall be in flows shall be in operation.
operation.
SR 3.4. 1.1 --------------- NOTE -------------- SR 3.4.1.1 --------------- NOTE -----------
Not required to be performed until Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after both recirculation loops 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after both recirculation loops are in operation. are in operation.
Verify the following recirulation pump Verify recirculation loop jet pump flow speed match criteria are satisfied: mismatch with both recirculation loops
- a. The recirculation pump speeds are in operations is:
< 20% of each other when operating a. < 10% of rated core flow when at < 75% of rated core flow; and operating at < 75% of rated core
- b. The recirculation pump speeds are flow; and
< 10% of each other when operating b. < 5% of rated core flow when at ? 75% of rated core flow. operating at _>75% of rated core flow.
In summary, the overall affect of the proposed amendment is to implement more conservative requirements associated with recirculation loop operation. These requirements assure that the mismatch between recirculation loop flows remains bounded by existing design bases analyses.
These changes are consistent with the current version of the Standard Technical Specifications (i.e., Reference 1: NUREG-1433, Revision 3.1).
For convenience, Enclosure 2 contains a marked-up version of the Unit 1 TSs showing the proposed changes. Since TS Sections 3.4.1 for Unit 1 and Unit 2 are identical, only the mark-up for Unit 1 is provided. Enclosures 3 and 4 provide typed versions of the Unit 1 and Unit 2 TSs, respectively. These typed TS pages are to be used for issuance of the proposed amendment.
Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., will make supporting changes to the TS Bases in accordance with TS 5.5.10, "Technical Specifications (TS) Bases Control Program." Enclosure 5 provides marked-up TS Bases pages for Unit 1. These pages are being submitted for information only and do not require issuance by the NRC.
BSEP 06-0136 Enclosure 1 Page 3 of 7 3.0 Background System Description/ApplicableSafety Analysis The Reactor Recirculation system is designed to provide a forced coolant flow through the core to remove heat from the fuel. The operation of the Reactor Recirculation system is an initial condition assumed in the design basis loss of coolant accident (LOCA). During a LOCA caused by a recirculation loop pipe break, the intact loop is assumed to provide coolant flow during the first few seconds of the accident. The initial core flow decrease is rapid because the recirculation pump in the broken loop ceases to pump reactor coolant to the vessel almost immediately. The pump in the intact loop coasts down relatively slowly. This pump coastdown governs the core flow response for the next several seconds until the jet pump suction is uncovered. The LOCA analysis assumes that both loops are operating at the same flow prior to the accident. However, the LOCA analysis was reviewed for the case with a flow mismatch between the two loops, with the pipe break assumed to be in the loop with the higher flow. While the flow coastdown and core response are potentially more severe in this assumed case (i.e., since the intact loop starts at a lower flow rate and the core response is the same as if both loops were operating at a lower flow rate), a small mismatch has been determined to be acceptable based on engineering judgment. The recirculation system is also assumed to have sufficient flow coastdown characteristics to maintain fuel thermal margins during abnormal operational transients.
Need for Change On October 27, 2006, as documented in Nuclear Condition Report 210701, CP&L determined that the existing SR 3.4.1.1, which verifies that recirculation pumps speeds are within 20% of each other when operating at less that 75% of rated core flow or within 10% of each other when operating at greater than or equal to 75% of rated core flow, does not provide adequate assurance that the recirculation loops are operating within the initial conditions of the existing LOCA analysis. To be bounded by the existing LOCA analysis, SR 3.4.1.1 must verify that for core flows less than 75% of rated, the loop flows shall be within 10% of rated core flow and for flows greater than or equal to 75% of rated, the loop flows shall be within 5% of rated core flow.
4.0 Technical Analysis The intent of LCO 3.4.1 and SR 3.4.1.1 is to ensure that the Reactor Recirculation system is operated within the bounds of the existing LOCA analysis, which assumes that both loops are operating at essentially the same flow prior to an accident. For BSEP, GE Nuclear Energy has determined (i.e., Reference 2) that the LOCA analysis assumption is met, for core flows less than 75% of rated, when the recirculation loop flows are operating within 10% of rated core flow and, for flows greater than or equal to 75% of rated, when the recirculation loop flows are within 5%
of rated core flow. The same GE Nuclear Energy document indicates that a 5% mismatch in terms of core flow conservatively equates to a 10% mismatch in terms of either loop flow or
BSEP 06-0136 Enclosure 1 Page 4 of 7 pump speed. Based on this guidance, the existing LCO 3.41 and SR 3.4.1.1 requirements were established.
In October 2006, Operations personnel noted that for a small indicated difference in recirculation pump speeds the deviation in loop flow was larger than expected. Based on this observation, Engineering initiated an evaluation of the bases for the criteria established in SR 3.4.1.1. As a result of the evaluation, three concerns were identified with the existing methodology of determining recirculation loop mismatch. The following discussion addresses each area of concern, from most significant to least significant.
Core Flow to RecirculationPump Speed Correlation The GE Nuclear Energy guidance indicated that recirculation pump speeds were to be within 20% of each other for core flows less than 75% of rated or within 10% of each other for core flows greater than or equal to 75% of rated. This was based on the determination that a 5%
mismatch in terms of core flow conservatively equates to a 10% mismatch in terms of recirculation pump speed. For this 5% core flow to 10% recirculation pump speed correlation to be accurate, the mismatch must be determined based on a ratio of one recirculation pump's speed to the other pump's speed. When SR 3.4.1.1 was implemented at BSEP, the procedure merely subtracted one loop's pump speed from the other loop's pump speed. This effectively doubled the mismatch when equated to core flow.
Hydraulic Interaction When the GE Nuclear Energy guidance was issued, a one-to-one relationship between speed and flow was assumed to exist based on the pump affinity relationship, which indicates that as the speed of a pumps is changed, the pump flow change will be proportional and the pump differential pressure (dP) change will be proportional to the square of the change in speed.
However, when a small speed mismatch occurs, the interaction between dPs causes a greater than one-to-one flow change. The potential for this hydraulic interaction was not clearly addressed in the GE Nuclear Energy guidance and, as a result, was overlooked by CP&L when developing TS 3.4.1.
Scaling The GE Nuclear Energy guidance indicated the potential need for scaling to account for conditions where the recirculation pump speed scale (i.e., 0 to 100% pump speed) is offset from the 0 to 100% rated core flow range. For example, on Unit 1, 86% to 87% recirculation pump speed is required to achieve 100% of rated core flow and, on Unit 2, 94% to 95% recirculation pump speed is required to reach 100% of rated core flow. Again, the scaling issue was not clearly addressed in the GE Nuclear Energy guidance and, as a result, was overlooked by CP&L when developing TS 3.4.1.
BSEP 06-0136 Enclosure 1 Page 5 of 7 Conclusion The above factors resulted in the potential that, although meeting the requirements of SR 3.4.1.1, the operating recirculation loops could, in fact, be outside the bounds of the LOCA analysis with respect to core flow.
To remedy this condition, the LCO requirements of TS 3.4.1 and SR 3.4.1.1 are being revised to directly monitor recirculation loop jet pump flows, consistent with the LOCA analysis assumption as well as the current version of the Standard Technical Specifications (i.e.,
NUREG 1433, Revision 3.1).
5.0 Regulatory Safety Analysis 5.1 No Significant Hazards Consideration CP&L has evaluated whether or not a significant hazards consideration is involved with the proposed amendments by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response:. No The proposed amendment implements more conservative requirements associated with recirculation loop operation. Specifically, the LCO requirements of TS 3.4.1 and SR 3.4.1.1 are being revised to directly monitor recirculation loop jet pump flows versus recirculation pump speed, eliminating potential non-conservatism associated with relating recirculation loop jet pump flow to recirculation pump speed. These requirements assure that the mismatch between recirculation loop jet pump flows are bounded by the existing design bases analyses. As a result, the proposed change ensures that the consequences of a design bases LOCA remain within the existing evaluation.
The proposed change does not involve a physical change to the Reactor Recirculation system, nor does it alter the assumptions of the accident analyses. Therefore the probability of an accident previously evaluated is not affected.
Based on the above, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No
BSEP 06-0136 Enclosure 1 Page 6 of 7 The proposed change does not involve a physical change to the Reactor Recirculation system, nor does it alter the assumptions of the accident analyses. The implementation of more conservative requirements associated with recirculation loop operation does not introduce any new failure modes. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No The proposed amendment implements more conservative requirements associated with recirculation loop operation. These requirements ensure that the Reactor Recirculation system is operated consistent with the initial conditions of the existing design bases analyses. Since the design bases analyses assumptions are unchanged, the proposed change does not involve a reduction in a margin of safety.
Based on the above, CP&L concludes that the proposed amendments present no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
5.2 Applicable Regulatory Requirements/Criteria The Commission's regulatory requirements related to the content of the TSs are set forth in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, "Technical specifications."
This regulation requires that the TS include items in five specific categories. These categories include (1) safety limits, limiting safety system settings and limiting control settings, (2) limiting LCOs, (3) SRs, (4) design features, and (5) administrative controls. Additionally, Criterion 2 of 10 CFR 50.36(c)(2)(ii) requires a limiting condition for operation to be established for a process variable, design feature, or operating restriction that is an initial condition of a design-basis accident (DBA) or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. The proposed change ensures that the LCO and SR associated with operation of the Reactor Recirculation system establish conditions that are consistent with the initial conditions assumed in the LOCA analysis.
The BSEP design was reviewed for construction under the "General Design Criteria for Nuclear Power Plant Construction" issued for comment by the AEC in July 1967 and is committed to meet the intent of the General Design Criteria (GDC), published in the Federal Register on May 21, 1971, as Appendix A to 10 CFR Part 50.
Criterion 10, "Reactor Designs," requires that the reactor core and associated coolant, control, and protective systems be designed with appropriate margins to assure that specified acceptable fuel design limits are not exceeded during normal operation and anticipated operational occurrences. The proposed change does not affect BSEP's compliance with the intent of
BSEP 06-0136 Enclosure 1 Page 7 of 7 GDC 10. Rather, it imposes TS requirements to ensure that the operation of the Reactor Recirculation system is within the bounds of the existing LOCA analysis. This ensures that fuel design limits are not exceeded during normal operation and anticipated operational occurrences.
6.0 Environmental Considerations 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 effluent 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.
7.0 References
- 1. NUREG-1433, Revision 3.1, "Standard Technical Specifications General Electric Plants, BWR/4," dated December 1, 2005.
- 2. Letter (KFC-37-90) from K. F. Cornewll (GE Nuclear Energy) to Bruce Morgan (CP&L),
"Final SLO Operational Guideline Summary," dated April 16, 1990.
BSEP 06-0136 Enclosure 2 Marked-up Technical Specification Pages - Unit 1
Recirculation Loops Operating 3.4.1 3.4 REACTOR CC )OLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating c h Two recirculation loops with matched ........... e-'
' d e shall be in LCO 3.4.1 operation, OR One recirculation loop may be in operation provided the following limits are applied when the associated LCO is applicable:
- a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," single loop operation limits specified in the COLR;
- b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," single loop operation limits specified in the COLR; and
- c. LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation,"
Function 2.b (Average Power Range Monitors Simulated Thermal Power-High), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation.
APPLICABILITY: MODES 1 and 2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Satisfy the requirements of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> not met. the LCO.
(continued)
Brunswick Unit 1 3.4-1 Amendment No.-i$I
Recirculation Loops Operating 3.4.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not met.
OR No recirculation loops in operation.
Brunswick Unit 1 3.4-2 Amendment
BSEP 06-0136 Enclosure 3 Typed Technical Specification Pages - Unit 1
Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation, I OR One recirculation loop may be in operation provided the following limits are applied when the associated LCO is applicable:
- a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," single loop operation limits specified in the COLR;
- b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," single loop operation limits specified in the COLR; and
- c. LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation,"
Function 2.b (Average Power Range Monitors Simulated Thermal Power-High), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation.
APPLICABILITY: MODES 1 and 2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Satisfy the requirements of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> not met. the LCO.
(continued)
Brunswick Unit 1 3.4-1 Amendment No. I
Recirculation Loops Operating 3.4.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not met.
OR No recirculation loops in operation.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 ----------------------- NOTE----------------
Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after both recirculation loops are in operation.
Verify recirculation loop jet pump flow mismatch with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> both recirculation loops in operation:
- a. _<10% of rated core flow when operating at
< 75% of rated core flow; and
- b. < 5% of rated core flow when operating at
> 75% of rated core flow.
Brunswick Unit 1 3.4-2 Amendment No. I
BSEP 06-0136 Enclosure 4 Typed Technical Specification Pages - Unit 2
Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation, I OR One recirculation loop may be in operation provided the following limits are applied when the associated LCO is applicable:
- a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," single loop operation limits specified in the COLR;
- b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," single loop operation limits specified in the COLR; and
- c. LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation,"
Function 2.b (Average Power Range Monitors Simulated Thermal Power-High), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation.
APPLICABILITY: MODES 1 and 2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Satisfy the requirements of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> not met. the LCO.
(continued)
Brunswick Unit 2 3.4-1 Amendment No.
Recirculation Loops Operating 3.4.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not met.
OR No recirculation loops in operation.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 -- ------------- -.----------------- NOTE Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after both recirculation loops are in operation Verify recirculation loop jet pump flow mismatch with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> both recirculation loops in operation:
- a. _<10% of rated core flow when operating at
< 75% of rated core flow; and
- b. _ 5% of rated core flow when operating at
> 75% of rated core flow.
Brunswick Unit 2 3.4-2 Amendment No. I
BSEP 06-0136 Enclosure 5 Marked-up Technical Specification Bases Pages - Unit 1 (For Information Only)
Recirculation Loops Operating B 3.4.1 BASES APPLICABLE A plant specific LOCA analysis has been performed assuming only one SAFETY ANALYSES operating recirculation loop. This analysis has demonstrated that, in the (continued) event of a LOCA caused by a pipe break in the operating recirculation loop, the Emergency Core Cooling System response will provide adequate core cooling, without the requirement to modify the APLHGR requirements (Ref. 3). However, the COLR may require APLHGR limits to restrict the peak clad temperature for a LOCA with a single recirculation loop operating below the corresponding temperature for both loops operating.
The transient analyses of Chapter 15 of the UFSAR have also been performed for single recirculation loop operation (Ref. 3) and demonstrate sufficient flow coastdown characteristics to maintain fuel thermal margins during the abnormal operational transients analyzed without the requirement to modify the MCPR requirements. During single recirculation loop operation, modification to the Reactor Protection System (RPS) average power range monitor (APRM) Simulated Thermal Power-High Allowable Value is required to account for the different analyzed limits between two-recirculation drive flow loop operation and operation with only one loop. The APRM channel subtracts the AW value from the measured recirculation drive flow to effectively shift the limits and uses the adjusted recirculation drive flow value to determine the APRM Simulated Thermal Power-High Function trip setpoint.
Recirculation loops operating satisfies Criterion 2 of 10 CFR 50.36(c)(2)(ii) (Ref. 4).
LCO Two recirculation loops -are matched normally within required the tolimits be inspecified operationinwith their SR 3.4.1.1 to ensure that during a LOCA caused by a break of the piping of one recirculation loop the assumptions of the LOCA analysis are satisfied. Alternately, with only one recirculation loop in operation, modifications to the required APLHGR limits (LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)"), MCPR limits (LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)"), and APRM Simulated Thermal Power-High Allowable Value (LCO 3.3.1.1), as (continued)
Brunswick Unit 1 B 3.4.1-3 Revision No. -3,P
Recirculation Loops Operating B 3.4.1 BASES LCO applicable, must be applied to allow continued operation. The COLR (continued) defines adjustments or modifications required for the APLHGR and MCPR limits for the current operating cycle.
APPLICABILITY In MODES 1 and 2, requirements for operation of the Reactor Coolant Recirculation System are necessary since there is considerable energy in the reactor core and the limiting design basis transients and accidents are assumed to occur.
In MODES 3, 4, and 5, the consequences of an accident are reduced and the coastdown characteristics of the recirculation loops are not important.
ACTIONS A.1 With the requirements of the LCO not met, the recirculation loo s must be hould a LOCA occur with one recirculation loop not in operation, the core flow coastdown and resultant core response may not be bounded by the acientordt analyses. Therefore, LOCA ocrering wuingthi only a limited time mtimhedlpGieriodon is allowed to restore pumpasonabletime t the inoperable loop to operating status.
Alternatively,complte ifReqiredActio the te single loop (i~., reet t of requirements apTiabe ethe oa LCO are '-paptvso appliedshetpit to operating limits and RPS setpoints, as applicable, operation with only one recirculation loop would satisfy the requirements of the LCO and the initial conditions of the accident sequence.
The 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Completion Time is based on the low probability of an accident occurring during this time period, on a reasonable time to complete the Required Action (i.e., reset the applicable limits or setpoints for single recirculation loop operation), and on frequent core monitoring by operators allowing abrupt changes in core flow conditions to be quickly (continued)
+/-p
~0 ~ {~t~ o-f f4e b&io Brunswick 1t Uni B 3..- evso o Brunswick Unit 1 B 3.4.1-4 Revision No. -3ý
Recirculation Loops Operating B 3.4.1 BASES ACTIONS A.1 (continued)
I ILC This Required Actior idoes not require tripping th~e recirculation pum*
~ ~ to lo-cst pu-mp cpc
-0(sp "Ap-'*o( tk
- L u,,. recirc,-bti.on I.I ! 't c'*. I ':p'-mps
- -,. are........ .......... ........... Fi...g d2Mate 1&.L.. ct:-
foto " criteri- QcCLGRG, lew fie f]It tI). ..* ¢k " ; vibration of the jet pi umps. If zero or reverse flow is detected, the condition should be alleviated by changing pump speeds to re-establish
- tLq~j*
- . t* iC)*.** forward flow.
-. With no recirculatior loops in operation or the Required Action and 1Q-Y9 c -r,*'t.* J associated Completiion Time of Condition A not met, the plant must be
'..' brought to a MODE in which the LCO does not apply. To achieve this
,og o 7/O¶Y" status, the plant mu st be brought to MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. In this C--evI--w-.*C.ay.
condition, the recirctulation loops are not required to be operating because ZoC.L)ur 4'e, eLo- 1" L of the reduced seve rity of DBAs and minimal dependence on the f( . fa t* 'recirculation loop co astdown characteristics. The allowed Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full pc wer conditions in an orderly manner and without challenging plant sy stems.
SURVEILLANCE SR 3.4.1.1 REQUIREMENTS This SR ensures the recirculation pump
) At low core flow (i.e., < 75% of raite5oefiow),'theMCPR pfZ ._I fI5.Ž
- requirements provide larger margins to the fuel cladding integrity Safety av-* W ,t Limit such that the potential adverse effect of early boiling transition during a LOCA is reduced. A larger__t ... e..
laui
, * , T* 4* -G/ Gorn flow.
S u r -c!! a R cT-ho c, c crccirculatin ns e r -ati. b pumAp sSpzcdcAc~d s m~ateh s -AtO;! cuod tA ; c cRGriteria-,- p ~ i- m e3 thic At c'h
- c~~--sen'atively el-ates to t~he 650 ,mate~hcFitcr-In ill tar, ,19 Of reercewatoon
_(continued)
Brunswick Unit 1 B 3.4.1-5 Revision No. e1ý"1
Recirculation Loops Operating B 3.4.1 SURVEILLANCE SR 3.4. 1.1 REQUIREMENTS spoodGop4a4e
@G.F61at@
L.*v*-fkl*-. c[{'-+L.._
bo rccircula:tion eirculationR Fon pump speeds. if the diff cer e tm. 1 Id,,- .... pu-mp
- .. ...poadc
, . ... ocoocdc
.. tho the ma2tch te cri.tcria, (I tho
.. .. wi..
.:th t the-I is considered not in operation. T R is not required when both loops are not in operation since th*
are meaningless during single loop or natural circulation operation. The tk- )m- LLtgC. Surveillance must be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after both loops are in 1o0 LsCr yi10 U operation. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is consistent with the Surveillance Frequency for jet pump OPERABILITY verification and has been shown byopera experience to be adequate to detect off normal) a timely manner.
REFERENCES 1. UFSAR, Section 5.4.1.3.
- 2. UFSAR, Chapter 15.
- 3. NEDC-31776P, Brunswick Steam Electric Plant Units 1 and 2 Single Loop Operation, February 1990.
- 4. 10 CFR 50.36(c)(2)(ii).
Brunswick Unit 1 B 3.4.1-6 Revision No.--3-?L/1