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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] |
Text
Progress Energy 0 Cornelius J. Gannon Vice President Brunswick Nuclear Plant Progress Eneryy Carolinas. Inr.
AUG 1 6 2004 SERIAL: BSEP 04-0091 10 CFR 50.90 TSC-2004-02 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit No. 2 Docket No. 50-324/License No DPR-62 Request for License Amendment - Addition of TRACG Methodology for Determining Core Operating Limits Ladies and Gentlemen:
In accordance with the Code of Federal Regulations, Title 10, Part 50.90, Carolina Power & Light (CP&L) Company, now doing business as Progress Energy Carolinas, Inc.,
(PEC) is requesting a revision to the Technical Specifications for the Brunswick Steam Electric Plant (BSEP), Unit No. 2. The proposed change adds topical report NEDE-32906P-A, "TRACG Application for Anticipated Operational Occurrences (AOO)
Transient Analyses," to the documents listed in TS 5.6.5 describing the approved methodologies used to determine the core operating limits. An evaluation of the proposed license amendment is provided in Enclosure 1.
PEC 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.
Unit 2 will be unable to resume power operation following Refueling Outage 16 without NRC approval for inclusion of the TRACG methodology in Technical Specification 5.6.5.b. Therefore, the NRC is requested to issue the requested license amendment no later than January 31, 2005. PEC requests that the amendment, once approved, be issued effective immediately, to be implemented prior to resuming operation from Unit 2 Refueling Outage 16 for Cycle 17.
CP&L is providing, in accordance with 10 CFR 50.91(b), the State of North Carolina a copy of the proposed license amendments.
P.O.Box 10429 Southport, NC 28461 T> 910.457.3698 F> 910.457.2803
Document Control Desk BSEP 04-0091 / Page 2 No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Mr. Edward T. ONeil, Manager - Support Services, at (910) 457-3512.
Sincerely, WRM/wrm
Enclosures:
- 1. Evaluation of License Amendment Request
- 2. Marked-up Technical Specification Pages - Unit 2
- 3. Typed Technical Specification Pages - Unit 2
- 4. List of Regulatory Commitments Cornelius J. Gannon, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, and agents of Carolina Power &
Light Company.
Notary (Seal) .
My commission expires: 5 9-
Document Control Desk BSEP 04-0091 / Page 3 cc (with enclosures):
U. S. Nuclear Regulatory Commission, Region II AI'TN: 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 ATTN: Ms. Brenda L. I.zzafari (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 Environmc.-t and Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7221
BSEP 04-0091 Enclosure 1 Page 1 of 5 Evaluation of License Amendment Request
Subject:
Request for License Amendment - Addition of TRACG Methodology for Determining Core Operating Limits 1.0 Description of Proposed Change The proposed change will revise the Appendix A Technical Specifications for Operating License DPR-62 to add General Electric Nuclear Energy (CENE) licensing topical report NEDE-32906P-A as an approved analytical method for determining core operating limits.
Currently, TS 5.6.5.b requires that the listed analytical methods, which have been previously reviewed and approved by the NRC, be used to determine the core operating limits. At present, only the latest approved version of GENE licensing topical report NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel," otherwise referred to as GESTAR-IH, is listed.
The proposed change revises Technical Specification 5.6.5.b to add GENE licensing topical report NEDE-32906P-A, "TRACG Application for Anticipated Operational Occurrences (AOO)
Transient Analyses." This document describes the application of the TRACG computer code for determining core operating limits forAOO transient analyses.
The specific wording of the proposed change follows; the change made is bolded.
5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. NEDE-2401 1-P-A, "General Electric Standard Application for Reactor Fuel," (latest approved version).
- 2. NEDE-32906P-A, "TRACG Application for Anticipated Operational Occurrences (AOO) Transient Analyses,"
approved version as specified in the COLR.
2.0 Discussion of Licensing Methodology The BSEP, Unit 2 Cycle 17 core thermal/hydraulic analysis will be performed by Global Nuclear Fuel - Americas, LLC (GNF)-A using plant-specific and cycle-specific fuel and core parameters and the NRC-approved methodologies included in GESTAR-IH. In addition to the methods currently approved in GESTAR-iH, GNF-A also plans to use the TRACG code, described in GENE licensing topical report NEDE-32906P-A, for the BSEP Unit 2 Cycle 17 core analysis.
BSEP 04-0091 Enclosure 1 Page 2 of 5 The TRACG code is a thermal/hydraulic analysis code intended to be used in realistic analyses of abnormal operational occurrences. The TRAC family of codes began as a pressurized water reactor analysis code developed for the NRC at Los Alamos National Laboratory. A boiling water reactor (BWR) version of the code was developed jointly by the NRC and GENE at the Idaho National Engineering Laboratory (INEL) as TRAC-BD1I/MOD1. GENE has developed a proprietary version of the code designated as TRACG TRACG is a multi-dimensional, two-fluid reactor thermal-hydraulics analysis code with three-dimensional neutron kinetics capability. The code is designed to perform in a realistic manner with conservatism added, where appropriate, via the input specifications.
By letter dated January 25, 2000 (i.e., ADAMS Accession Number ML003680922), GENE and its subsidiary GNF-A submitted licensing topical report NEDE-32906P for NRC review and approval. NRC approval of NEDE-32906P was subsequently issued by letter dated October 22, 2001 (i.e., ADAMS Accession Number ML012770430).
By letter dated August 6, 2003, GENE submitted an update to GESTAR-il which incorporates additional NRC-approved codes, including TRACGQ into the GNF-A licensing methodology.
A portion of these GESTAR-II changes were approved by the NRC in a letter dated July 16, 2004 (i.e., ADAMS Accession Number ML042010353); however, Progress Energy Carolinas, Inc. (PEC) understands that GENE does not plan to issue the amendment to GESTAR-II until the NRC completes review of the remaining changes. Thus, until GENE can issue the approved amendment to GESTAR-II, and thus incorporate NEDE-32906P-A for use, PEC must request the change to BSEP TS 5.6.5.b in order to the use NEDE-32906P. If the NRC completes review and approval of the GENE updates to GESTAR-Il prior to issuance of the PEC license amendment, the proposed change to BSEP TS 5.6.5.b will no longer be needed.
3.0 Regulatory Safety Analysis 3.1 No Significant Hazards Consideration Determination PEC has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change to TS 5.6.5.b will add General Electric Nuclear Energy topical report NEDE-32906P-A, "TRACG Application for Anticipated Operational Occurrences (AOO)
Transient Analyses," to the list of documents describing approved methodologies for determining core operating limits. NRC review and acceptance of the TRACG
BSEP 04-0091
- Enclosure 1 Page 3 of 5 methodology is documented in an October 22, 2001, letter and associated safety evaluation issued to General Electric Nuclear Energy (i.e., refer to ADAMS Accession Numbers ML012740390 and ML012740161). Analyzed events are assumed to be initiated by the failure of plant structures, systems, or components. The core operating limits, which are developed using the topical report being added, ensure that the integrity of the fuel will be maintained during normal operations and that design requirements will continue to be met.
The proposed change does not involve physical changes to any plant structure, system, or component. Therefore, the probability of occurrence for a previously analyzed accident is not significantly increased.
The consequences of a previously analyzed accident are dependent on the initial conditions assumed for the analysis, the behavior of the fuel during the analyzed accident, the availability and successful functioning of the equipment assumed to operate in response to the analyzed event, and the setpoints at which theseI actions are initiated. Use of the analytical methodologies described in the topical report being added to TS 5.6.5.b will ensure that applicable design and safety analyses acceptance criteria are met. Use of these NRC-approved methodologies does not affect the performance of any equipment used to mitigate the consequences of an analyzed accident. As a result, no analysis assumptions are violated and there are no adverse effects on the factors that contribute to offsite or onsite dose as the result of an accident. Use of the approved methodologies described in the topical report being added to TS 5.6.5.b ensures that plant structures, systems, or components are maintained consistent with the safety analysis and licensing bases. Based on this evaluation, there is no significant increase in the consequences of a previously analyzed event.
Therefore, the proposed change adding General Electric Nuclear Energy'licensing topical report NEDE-32906P-A to the TS 5.6.5.b list of documents describing approved methodologies for determining core operating limits 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 The proposed change adding licensing topical report NEDE-32906P-A to TS 5.6.5.b, and the use of the analytical methods described therein, does not involve any physical alteration of plant systems, structures, or components, other than allowing for fuel and core designs in accordance with NRC approved methodologies. The proposed methodology continues to meet applicable criteria for core operating limit analysis. No new or different equipment is being installed. No installed equipment is being operated in a different manner. There is no alteration to the parameters within which the plant is normally operated or in the setpoints that initiate protective or mitigative actions. As a result no new failure modes are being introduced.
BSEP 04-0091 Enclosure 1 Page 4 of 5 Therefore, the proposed change adding General Electric Nuclear Energy licensing topical report NEDE-32906P-A to the TS 5.6.5.b list of documents describing approved methodologies for determining core operating limits 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 margin of safety is established through the design of the plant structures, systems, and components, through the parameters within which the plant is operated, through the establishment of the setpoints for the actuation of equipment relied upon to respond to an event, and through margins contained within the safety analyses. The proposed change adding General Electric Nuclear Energy licensing topical report NEDE-32906P-A to the TS 5.6.5.b list of documents describing approved methodologies for determining core operating limits does not impact the condition or performance of structures, systems, setpoints, and components relied upon for accident mitigation. The proposed change does not significantly impact any safety analysis assumptions or results. Therefore, the proposed change adding topical report NEDE-32906P-A to the TS 5.6.5.b list of documents describing approved methodologies for determining core operating limits does not result in a significant reduction in the margin of safety.
Based on the above, PEC concludes that the proposed amendment presents 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.
3.2 Applicable Regulatory Requirements/Criteria The BSEP design was reviewed for construction under the "General Design Criteria for Nuclear Power Plant Construction" issued for comment by the Atomic Energy Commission 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. Title 10 of the Code of Federal Regulations (10 CFR) establishes the fundamental regulatory requirements with respect to reactivity control systems. Specifically, GDC-10, "Reactor design," states, in part, that the reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded.
NRC Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications," provides guidance on modifying cycle-specific parameter limits in TS. The proposed change to TS 5.6.5.b adding GENE topical report NEDE-32906P-A to the list of documents describing approved methodologies for determining core operating limits is in compliance with the guidance specified in Generic Letter 88-16. Use of the approved TRACG methods helps ensure that appropriate fuel margins are maintained and fuel design limits are not exceeded.
' BSEP 04-0091 Enclosure 1 Page 5 of 5 In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
4.0 Environmental Evaluation 10 CFR 51.22(c)(9) identifies certain licensing and regulatory actions, which are eligible for categorical exclusion from the requirement to perform an environmental assessment. A proposed amendment to an operating license for a facility does not require an environmental assessment if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; or (3) result in 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.
5.0 Precedents By letter dated March 23, 2004 (ADAMS Accession Numbers ML040890673 and ML040900042), the NRC has previously approved an identical change for BSEP, Unit 1 incorporating GENE topical report NEDE-32906P-A into the list of documents describing approved methodologies for determining core operating limits.
BSEP 04-0091 Enclosure 2 Marked-up Technical Specification Pages - Unit 2
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
- 1. The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) for Specification 3.2.1;
- 2. The MINIMUM CRITICAL POWER RATIO (MCPR) for Specification 3.2.2;
- 3. The period based detection algorithm (PBDA) setpoint for Function 2.f, Oscillation Power Range Monitor (OPRM) Upscale, for Specification 3.3.1.1; and
- 4. The Allowable Values and power range setpoints for Rod Block Monitor Upscale Functions for Specification 3.3.2.1.
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. NEDE-2401 1-P-A, 'General Electric Standard Application for Reactor Fuel" (latest approved version).
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
(continued)
- 2. tEE-32e40(P-A, "TRACG C Ap An%+cipzatej Operati ono~l Occurrenices (Aoo)
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Brunswick Unit 2 5.0-20 Amendment No.2 I
. . f BSEP 04-0091 Enclosure 3 lyped Technical Specification Pages - Unit 2
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) -
5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
- 1. The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) for Specification 3.2.1;
- 2. The MINIMUM CRITICAL POWER RATIO (MCPR) for Specification 3.2.2;
- 3. The Allowable Value for Function 2.b, APRM Flow Biased Simulated Thermal Power-High, for Specification 3.3.1.1; and
- 4. The Allowable Values and power range setpoints for Rod Block Monitor Upscale Functions for Specification 3.3.2.1.
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. NEDE-2401 1-P-A, "General Electric Standard Application for Reactor Fuel" (latest approved version).
- 2. NEDE-32906P, "TRACG Application for Anticipated Operational Occurrences (AOO) Transient Analyses," approved version as specified in the COLR.
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
(continued)
Brunswick Unit 2 5.0-20 Amendment No.
BSEP 04-0091 Enclosure 4 List of Regulatory Commitments The following table identifies those actions committed to by Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc. (PEC), in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. Please direct questions regarding these commitments to the Manager -
Support Services at the Brunswick Steam Electric Plant.