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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:Report
MONTHYEARRA-22-0165, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 242022-06-0909 June 2022 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24 RA-22-0134, Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data2022-05-25025 May 2022 Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data RA-21-0198, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 252021-06-21021 June 2021 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 25 RA-21-0176, Cycle 24 Mellla+ Eigenvalue Tracking Data2021-06-0707 June 2021 Cycle 24 Mellla+ Eigenvalue Tracking Data RA-20-0353, Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1)2021-02-24024 February 2021 Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1) RA-20-0347, 10 CFR 71.95 Report on the 3-60B Cask2020-11-16016 November 2020 10 CFR 71.95 Report on the 3-60B Cask RA-19-0479, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-12-31031 December 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0411, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-10-23023 October 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0338, Pressure and Temperature Limits Report for Unit Nos. 1 and 22019-08-15015 August 2019 Pressure and Temperature Limits Report for Unit Nos. 1 and 2 RA-19-0243, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-07-0202 July 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 RA-19-0240, Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request2019-05-29029 May 2019 Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request 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-18-0100, Request for License Amendment Regarding Application of Advanced Framatome Methodologies2018-10-11011 October 2018 Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-18-0131, Technical Requirements Manual, Revision 662018-08-13013 August 2018 Technical Requirements Manual, Revision 66 ML18249A1592018-08-13013 August 2018 Technical Requirements Manual, Revision 73 RA-18-0024, Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2018-05-29029 May 2018 Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report BSEP 18-0044, 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 ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 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. ML16223A7252016-08-17017 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events) CAC Nos. MF4467 and MF4468) ML18250A0022016-08-11011 August 2016 Technical Requirements Manual, Revision 70 ML18250A0032016-08-11011 August 2016 Technical Requirements Manual, Revision 63 ML16257A4112016-07-31031 July 2016 DUKE-0B21-1104-000(NP), Safety Analysis Report for Brunswick Steam Electric Plant, Units 1 and 2, Maximum Extended Load Line Limit Analysis Plus. ML16041A4352016-03-0101 March 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force ML16257A4062015-12-31031 December 2015 ANP-3106(NP), Revision 2, Brunswick Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for Atrium 10XM Fuel for Mellla+ Operation. ML15275A2902015-09-30030 September 2015 Areva, Inc., - ANP-3397NP, Revision 0, Brunswick, Unit 2, Atrium 11 Lead Test Assemblies Design & Licensing Summary Report. BSEP 16-0056, ANP-3108(NP), Revision 1, Applicability of Areva BWR Methods to Brunswick Extended Power Flow Operating Domain.2015-07-31031 July 2015 ANP-3108(NP), Revision 1, Applicability of Areva BWR Methods to Brunswick Extended Power Flow Operating Domain. ML16257A4082015-07-31031 July 2015 ANP-3105(NP), Revision 1, Brunswick Units 1 and 2 LOCA Break Spectrum Analysis for Atrium 10XM Fuel for Mellla+ Operation. BSEP 15-0004, Enclosure 3 - Areva Operability Assessment. (CR 2014-7395)2015-01-13013 January 2015 Enclosure 3 - Areva Operability Assessment. (CR #2014-7395) BSEP 14-0131, Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident2014-12-18018 December 2014 Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident ML14297A2662014-10-24024 October 2014 Record of Review, Brunswick Steam Electric Plant, Units 1 and 2, LAR Attachment U- Table U-1 Internal Events PRA Peer Review- Facts and Observations (F&Os), 10/24/14 BSEP 14-0101, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2014-09-0404 September 2014 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors BSEP 14-0093, Report of 10 CFR 50.59 Evaluations and Commitment Changes2014-08-14014 August 2014 Report of 10 CFR 50.59 Evaluations and Commitment Changes ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 BSEP 14-0028, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi A2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid ML13220A0902013-11-22022 November 2013 Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13317A5922013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Brunswick Steam Electric Plant, Units 1 and 2, TAC Nos.: MF0975 and MF0976 ML13277A0412013-09-19019 September 2013 Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition ML16257A4072013-05-31031 May 2013 ANP-3013(NP), Revision 0, Brunswick Unit 1 Cycle 19 Fuel Cycle Design Mellla+ Operating Domain. BSEP 13-0030, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2013-02-28028 February 2013 Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events BSEP 13-0002, Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact2013-01-14014 January 2013 Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact ML13031A0112013-01-11011 January 2013 Engineering Information Record, Document No. 51-9196989-000, Supplemental Information for Brunswick SAFLIM3D Submittal: Impact of Assemblies Outside Existing Channel Bow Fast Fluence Gradient Database BSEP 12-0133, Document No. 51-9195058-000, Areva Input to Process Energy: Follow-Up to SAFLIM3D LAR Request for Additional Information 3, Enclosure 3 to BSEP 12-01332012-11-27027 November 2012 Document No. 51-9195058-000, Areva Input to Process Energy: Follow-Up to SAFLIM3D LAR Request for Additional Information 3, Enclosure 3 to BSEP 12-0133 BSEP 12-0127, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident2012-11-27027 November 2012 Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident BSEP 12-0128, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation2012-11-14014 November 2012 Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation ML12321A3192012-11-0101 November 2012 1000771.402NP, Revision 2, Life Extension for Core Plate Plugs at Brunswick Nuclear Plant Unit 2. ML12065A3802012-03-26026 March 2012 Request to Reinitiate Section 7 Consultation for Atlantic Sturgeon at Brunswick Steam Electric Plant, Units 1 and 2 BSEP 12-0031, Areva Document ANP-3086(NP), Brunswick Units 1 and 2 SLMCPR Operability Assessment Critical Power Correlation for Atrium 10XM Fuel - Improved K-factor Model, Enclosure 20 to BSEP 12-00312012-02-29029 February 2012 Areva Document ANP-3086(NP), Brunswick Units 1 and 2 SLMCPR Operability Assessment Critical Power Correlation for Atrium 10XM Fuel - Improved K-factor Model, Enclosure 20 to BSEP 12-0031 ML12076A0632012-02-17017 February 2012 Areva Document No. 51-9177317-000, Brunswick Unit 1 Cycle 19 SLMCPR Analysis with SAFLIM3D Methodology, Engineering Information Record, Enclosure 8 to BSEP 12-0031 2022-06-09
[Table view] Category:Miscellaneous
MONTHYEARRA-22-0165, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 242022-06-0909 June 2022 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24 RA-21-0198, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 252021-06-21021 June 2021 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 25 RA-20-0353, Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1)2021-02-24024 February 2021 Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1) RA-19-0479, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-12-31031 December 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 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 ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 ML16223A7252016-08-17017 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events) CAC Nos. MF4467 and MF4468) ML16041A4352016-03-0101 March 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force BSEP 15-0004, Enclosure 3 - Areva Operability Assessment. (CR 2014-7395)2015-01-13013 January 2015 Enclosure 3 - Areva Operability Assessment. (CR #2014-7395) BSEP 14-0131, Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident2014-12-18018 December 2014 Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident ML14297A2662014-10-24024 October 2014 Record of Review, Brunswick Steam Electric Plant, Units 1 and 2, LAR Attachment U- Table U-1 Internal Events PRA Peer Review- Facts and Observations (F&Os), 10/24/14 BSEP 14-0101, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2014-09-0404 September 2014 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors BSEP 14-0093, Report of 10 CFR 50.59 Evaluations and Commitment Changes2014-08-14014 August 2014 Report of 10 CFR 50.59 Evaluations and Commitment Changes ML13277A0412013-09-19019 September 2013 Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition BSEP 13-0030, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2013-02-28028 February 2013 Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events BSEP 12-0127, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident2012-11-27027 November 2012 Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident BSEP 12-0128, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation2012-11-14014 November 2012 Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants BSEP 14-0007, 1707-01-F03, Rev. 3, Operability Assessment (CR2013-8241)2011-09-0808 September 2011 1707-01-F03, Rev. 3, Operability Assessment (CR#2013-8241) BSEP 11-0038, Renewed Facility Operating License and Cycle 20 Core Operating Limits Report2011-04-0808 April 2011 Renewed Facility Operating License and Cycle 20 Core Operating Limits Report ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages BSEP 10-0097, Report of 10 CFR 50.59 Evaluations and Commitment Changes2010-08-18018 August 2010 Report of 10 CFR 50.59 Evaluations and Commitment Changes ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1019305532009-12-14014 December 2009 NEI 07-07 NEI Groundwater Protection Initiative NEI Peer Assessment Report for Brunswick BSEP 09-0022, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation2009-02-23023 February 2009 Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation BSEP 08-0121, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2008-09-24024 September 2008 Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML0711000062006-12-0808 December 2006 Operational Safety Review Team (Osart) Mission and Follow-up Visit Report BSEP 06-0095, Report of 10 CFR 50.59 Evaluation and Commitment Changes2006-08-24024 August 2006 Report of 10 CFR 50.59 Evaluation and Commitment Changes BSEP 06-0075, Groundwater Questionnaire2006-07-28028 July 2006 Groundwater Questionnaire ML0614404872006-05-18018 May 2006 Submittal of 10-O Report for Quarterly Period Ending March 31, 2006 BSEP 05-0137, Core Operating Limits Report, Revision 2, Cycle 152005-11-14014 November 2005 Core Operating Limits Report, Revision 2, Cycle 15 BSEP 05-0110, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2005-08-31031 August 2005 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML0515903332005-05-31031 May 2005 Submittal of 10-Q Report ML0535300692005-05-0909 May 2005 Operational Safety Review Team (Osart) Mission to Brunswick Nuclear Plant 9-25 May 2005 BSEP 05-0018, Occupational Radiation Exposure Report for 20042005-04-20020 April 2005 Occupational Radiation Exposure Report for 2004 ML0434301332004-11-30030 November 2004 Submital of 10-Q Report ML0414602462004-05-19019 May 2004 Q Report for Period Ending 03/31/2004 ML0324716322003-08-22022 August 2003 Submittal of 10-Q Report ML0318909362003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Brunswick, Crys ML0317000272003-06-0606 June 2003 Submittal of 10-O Report ML19204A1621998-11-18018 November 1998 Enclosure 1 - Staff Evaluation Report of Individual Plant Examination of External Events (IPEEE) Submittal on Brunswick Steam Electric Plant (Bsep), Units 1 and 2 2022-06-09
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Brunswick Nuclear Plant P.O. Box 10429 ENERGY, Southport, NC 28461 10 CFR 50.59(d)(2)
August 14, 2014 Serial: BSEP 14-0093 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Report of 10 CFR 50.59 Evaluations and Commitment Changes Ladies and Gentlemen:
In accordance with 10 CFR 50.59(d)(2), Duke Energy Progress, Inc., is providing a report summarizing the 10 CFR 50.59 evaluations of changes, tests, and experiments implemented during the period from August 1, 2012, to July 31, 2014. This report is provided in Enclosure 1.
In addition, a summary of commitment changes since July 31, 2012 (i.e., the previous report of 10 CFR 50.59 Evaluations and Commitment Changes), made in accordance with Duke Energy's commitment management program (i.e., REG-NGGC-01 10, "Regulatory Commitments"), is provided in Enclosure 2.
No regulatory commitments are contained in this submittal. Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager - Regulatory Programs, at (910) 457-2487.
Sincerely, Annette H. Pope Director - Organizational Effectiveness Brunswick Steam Electric Plant TMS/tms
Enclosures:
- 1. Summary of Changes, Tests, and Experiments Requiring 10 CFR 50.59 Evaluations
- 2. Regulatory Commitment Change Summary Report
U.S. Nuclear Regulatory Commission Page 2 of 2 cc (with enclosures):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Victor M. McCree, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510
BSEP 14-0093
BSEP 14-0093 Enclosure 1 Page 1 of 18 Summary of Changes, Tests, and Experiments Requiring 10 CFR 50.59 Evaluations Table of Contents Activity Title Page Chlorine Tank Car Isolation Valve Removal 2 Supplemental Diesel Generator System Installation 3 Flood Protection Basis Update 4 Recirculating Motor Variable Frequency Drive Interposing Relays With Digital Feedwater Control System 5 Repair of Through-Wall Leak on 2-SW-22-30-R-l 6 Temporary Power Supply to the Unit 1 1D and lC Drywell Cooler Fan Motors 7 Replacement of Analog Ronan Components in the Augmented Off Gas System and the Digital Control System 8 Emergency Diesel Generator Margin Improvements - Ventilation Relay and Timing Upgrade 9 Modify Battery Maintenance Surveillance Test to Verify Adequate Voltage 10 Procedure 1SP-EC85198, Condensate Margin Confirmation 11 Transversing In-Core Probe Index Mechanism 1-C5 l-J1001C Limit Switch S2 Temporary Jumper Installation 12 Emergency Diesel Generator Exciter / Voltage Regulator Replacement 13 Reactor Feed Pump Rotating Assemblies and Diffusers.Replacement 14 Supplemental Diesel Generator System Installation Change Package Revision 15 Revise Battery Maintenance Surveillance Tests to Validate Voltage 16 Reactor Feed Pump Rotating Assemblies and Diffusers Replacement Revision 17 Supplemental Diesel Generator Modification Testing 18
BSEP 14-0093 Enclosure 1 Page 2 of 18
Title:
Chlorine Tank Car Isolation Valve Removal Evaluation Identification Number: Action Request 550615 Brief
Description:
The scope of this Engineering Change (EC) was to remove the chlorine tank car isolation valve and its adjacent piping since the Chlorination system is no longer in use.
Summary of 10 CFR 50.59 Evaluation:
This modification removed the chlorine railroad tank car isolation valve (2-CS-V 1) with the associated adjacent piping and caps the abandoned supply line from where it connected to the chlorine tank car prior to its removal. The chlorination system is no longer used and the chlorine tank car has been removed from the plant site so the isolation capability is no longer needed.
This change did not affect other safety significant equipment and had no effect on plant safety response.
Plant
References:
Engineering Change (EC) 87418 Updated Final Safety Analysis Review (UFSAR) Change Package 12FSAR-0 18
BSEP 14-0093 Enclosure 1 Page 3 of 18
Title:
Supplemental Diesel Generator System Installation Evaluation Identification Number: Action Request 579105 Brief
Description:
The scope of this change installs the Supplemental Diesel Generator (DGS) System, which provides a commercial grade, non-safety related supplemental three phase AC power source capable of supplying any of the four 4.16 kV emergency buses, via the 4.16 kV Balance of Plant (BOP) bus circuit path. It will supply power within one hour from the Station Blackout (SBO) event, with the capacity to bring the affected unit to cold shutdown.
Summary of 10 CFR 50.59 Evaluation:
This modification activity installs the Supplemental Diesel Generator (DGS) System, which provides a commercial grade, non-safety related supplemental three phase AC power source capable of supplying any of the four 4.16 kV emergency buses, via the 4.16 kV BOP bus circuit path. It will supply power within one hour from the Station Blackout (SBO) event, with the capacity to bring the affected unit to cold shutdown. The 4KV BOP bus impact during monthly testing is the most significant nuclear safety concern. This concern and other concerns were shown to be less than a minimal increase based on similar protective relaying and Emergency Diesel Generator (EDG) testing that has been performed for the life of the plant.
Plant
References:
EC 79694 Updated Final Safety Analysis Report (UFSAR) Change Package 12FSAR-024
BSEP 14-0093 Enclosure 1 Page 4 of 18
Title:
Flood Protection Basis Update Evaluation Identification Number: Action Request 587251 Brief
Description:
The scope of this change is to update the site flood protection basis.
Summary of 10 CFR 50.59 Evaluation:
The engineering change package updated the evaluation of a High Energy Line Break (HELB) with fire suppression system actuation and documents that essential instruments in the Residual Heat Removal (RHR) room may be submerged. A review of the submerged instruments found that either the function is not essential, or that documentation is available to show that the instrument is qualified for the conditions expected. The reactor and mitigation system response to this postulated event continues to be consistent with the original licensing basis evaluations of HELBs as was previously documented.
The description of the separation provided by the rooms in the reactor building is being updated.
The amount of separation provided remains adequate to prevent water from spilling over from one room into another during any of the flooding events that must be postulated. This continues to meet the functional objective of having redundant trains separated to prevent loss of function.
Plant
References:
EC 80408 Updated Final Safety Analysis Report (UFSAR) Change Package 13FSAR-024 UFSAR Change Package 13FSAR-032
BSEP 14-0093 Enclosure 1 Page 5 of 18
Title:
Recirculating Motor Variable Frequency Drive (VFD) Interposing Relays With Digital Feedwater Control System (DFWCS)
Evaluation Identification Number: Action Request 592382 Brief
Description:
The scope of this change is to evaluate the new failure modes associated with the installation of the interposing relays between the Recirculation Flow Control System (RFCS) and DFWCS.
Summary of 10 CFR 50.59 Evaluation:
Installation of the VFDs required installation of interposing relays to interface between existing plant equipment and the new control system. The interposing relays require AC power to operate and as such, system responses resulting from a loss of a 480 V E-bus have changed. A License Amendment is not required to implement this activity. This activity does introduce new system responses on the loss of a 480 V E-bus, but as shown in the evaluation, these responses are bounded by previous system responses.
Plant
References:
EC 90286
BSEP 14-0093 Enclosure I Page 6 of 18
Title:
Repair of Through-Wall Leak on 2-SW-22-30-R-1 Evaluation Identification Number: Action Request 595513 Brief
Description:
This evaluation evaluated the acceptability of performing a temporary repair of a through-wall leak and wall thinning in a 30" flange in the discharge piping of the Turbine Building Closed Cooling Water (TBCCW) heat exchanger.
Summary of 10 CFR 50.59 Evaluation:
The temporary repair consisted of welding a plate over the area of the through-wall leak. The evaluation determined that the installation of the temporary repair did not impact, in any way, the Service Water System's ability to perform its required safety related function.
Plant
References:
EC 90921 WO 213065-01
BSEP 14-0093 Enclosure 1 Page 7 of 18
Title:
Temporary Power Supply to the Unit 1 ID and 1C Drywell Cooler Fan Motors Evaluation Identification Number: Action Request 597894 Brief
Description:
This change provided temporary power to Drywell Cooler Supply Fans I-VA-ID I-SF-DW and 1-VA-1D2-SF-DW during the E3 bus outage and 1-VA-1CI-SF-DW and 1-VA-1C2-SF-DW during the E4 bus outage in order to make them functional during these periods.
Summary of 10 CFR 50.59 Evaluation:
Temporary power was used to power Drywell Cooler Supply Fans 1-VA-lD I-SF-DW and I-VA-1D2-SF-DW during the E3 bus outage and 1-VA-1C1-SF-DW and I-VA-1C2-SF-DW during the E4 bus outage in order to make them functional during these periods. The installation of temporary power at MCC 1XJ compartment EP 1 and EP2 for the duration of the E3/E7 bus outage or at MCC 1XK compartment ER6 and ER7 for the duration of the E4/E8 bus outage was found to be acceptable.
Plant
References:
WO 2124914 WO 2223200
BSEP 14-0093 Enclosure 1 Page 8 of 18
Title:
Replacement of Analog Ronan Components in the Augmented Off Gas (AOG) System and the Digital Control System (DCS)
Evaluation Identification Number: Action Request 610359 Brief
Description:
The scope of this change is to replace 72 obsolete installed RONAN X81 and X82 Series analog circuit cards, which perform various indication and control functions for 23 separate instrument loops in the AOG system with Honeywell Experion compatible modules that tie into the existing Honeywell DCS system to provide indication, control, and alarming for the AOG system.
Summary of 10 CFR 50.59 Evaluation:
The replacement of the existing analog Ronan components in the 23 AOG instrument loops with DCS and digitally emulated functions was shown to be acceptable and resulted in less than a minimal increase of malfunction, consequences, or accident initiation.
Plant
References:
EC 57844 EC 90171
BSEP 14-0093 Enclosure I Page 9 of 18
Title:
Emergency Diesel Generator (EDG) Margin Improvements - Ventilation Relay and Timing Upgrade Evaluation Identification Number: Action Request 625077 Brief
Description:
The scope of this change added a timer relay and interlocking relay to each Diesel Generator Building Ventilation (DGBVA) Supply Fan starter to provide a 34 second delay in the restart of the timer.
Summary of 10 CFR 50.59 Evaluation:
The change to add a DGBVA timer upgrade was found to be acceptable. The DGBVA supply fans energize automatically and are available to support operation of the diesel generators following EDG breaker closure. An analysis of DGBVA system performance shows the temperature rise in the Diesel Generator Building (DGB) resulting from a delay in the start time of the DGB supply fans is bounded by existing design calculations; therefore the integrity of the Systems, Structures, and Components (SSCs) served by the DGBVA system is maintained.
Plant
References:
EC 86413
BSEP 14-0093 Enclosure 1 Page 10 of 18
Title:
Modify Battery Maintenance Surveillance Test (MST) to Verify Adequate Voltage Evaluation Identification Number: Action Request 669364 Brief
Description:
The scope of this change was to update the DC System Load Calculation BNP-E-6.120 and revise the battery surveillance capacity tests for Unit 1. The change allows a higher voltage to be credited for equipment operation by verifying that the voltage during the first minute of the capacity tests are greater than those required for equipment operation. Making these changes required testing the batteries at a load current value closer to their design maximum.
Summary of 10 CFR 50.59 Evaluation:
The change to the first minute load profile from 916 A to 725 A in the service capacity and modified performance capacity tests was evaluated for technical acceptability. The modified performance capacity tests are performed on the Unit 1 batteries by 1MST-BAT1 1AFY, IMST-BAT1 1BFY, IMST-BAT 11CFY, and 1MST-BATI IDFY. This change performed a new load flow test to verify that the load demand on the batteries remained below 725 A with a corresponding battery voltage of 107 V. The previous battery voltage requirement was 105 V.
Additionally, at this current the corresponding battery voltage is sufficient that the design function of Systems, Structures, and Components (SSCs) important to safety will continue to be able to perform their design requirements. Based on the evaluation performed, it was determined that changing the first minute of the load profile maintains the design requirements of the facility as described in the Updated Final Safety Analysis Report (UFSAR).
Plant
References:
EC 94834
BSEP 14-0093 Enclosure 1 Page 11 of 18
Title:
Procedure 1SP-EC85198, Condensate Margin Confirmation Evaluation Identification Number: Action Request 678640 Brief
Description:
This procedure tested the Unit 1 Condensate and Feedwater System to document the condensate system performance of the redesigned and new condensate suction piping following the installation of new condensate pump suction lines. This data will be used to validate analysis, establish operational limits and margins, and improve simulator fidelity.
Summary of 10 CFR 50.59 Evaluation:
1SP-EC85198 and its associated Work Orders (WO) can be safely performed. The combination of procedural controls, simulator modeling, operator training, and past experience demonstrated that the evolution stays within design boundaries and a plant trip is unlikely, but bounded.
Plant
References:
Procedure 1SP-EC85198 WO 2241825 EC 85198
BSEP 14-0093 Enclosure 1 Page 12 of 18
Title:
Transversing In-Core Probe (TIP) Index Mechanism 1-C5 1-J001C Limit Switch (LS) S2 Temporary Jumper Installation Evaluation Identification Number: Action Request 681471 Brief
Description:
The scope of this temporary change is to provide a method to continue TIP traces on TIP C.
Summary of 10 CFR 50.59 Evaluation:
This modification involved TIP C operation with a modification to simulate LS S2 actuation at all times and compensatory measures required to minimize the impact of this change.
Administrative actions greatly reduced the risk of any complications and all conditions are bounded by existing plant design and subsequent equipment failures.
Plant
References:
EC 96160
BSEP 14-0093 Enclosure I Page 13 of 18
Title:
Emergency Diesel Generator (EDG) Exciter / Voltage Regulator Replacement Evaluation Identification Number: Action Request 681835 Brief
Description:
The scope of this change is to replace the existing General Electric (GE) Shunt Silicon Controlled Rectifiers (SCR) Excitation System with a Basler Stator Exciter Regulator-Current Boost (SER-CB) excitation system.
Summary of 10 CFR 50.59 Evaluation:
The Basler SER-CB contains the RA-70 (i.e., Reference Adjustor). The RA-70 is a microcontroller-based reference adjustor that provides a solid-state method of adjusting the setpoint value for the Basler Automatic Voltage Regulator (AVR). The replacement of the Motor Operated Potentiometer (MOP) with the new RA-70 is considered a digital upgrade. From a digital upgrade perspective, it has been determined that this proposed change does not require a License Amendment since this equipment replacement represents relatively simple digital equipment, the likelihood of software failure is judged to be no greater than hardware failure, and that the likelihood of common mode failures has not been increased.
The system dependability is adequate and the likelihood of software failure occurring in multiple diesel generator governors is low relative to the likelihood of a hardware failure. Based on the dependability and redundancy of the emergency diesel system combined with the low probabilities of the other events identified above, the software common cause failures in the exciter RA-70 is not a significant concern.
Plant
References:
EC 70989
BSEP 14-0093 Enclosure 1 Page 14 of 18
Title:
Reactor Feed Pump (RFP) Rotating Assemblies and Diffusers Replacement Evaluation Identification Number: Action Request 682472 Brief
Description:
The scope of this change is to install new RFP impeller/diffuser assembly in each of the RFPs.
Summary of 10 CFR 50.59 Evaluation:
Based on the evaluation, there are minimal increases in the frequency and likelihood of occurrence of Reactor Feed Pump Turbine (RFPT) damage due to high turbine condensate level in the operating turbine casing following a loss of a single RFP during near full power operation.
The increases are considered minimal because procedures are being revised to lower allowable reactor power during single pump operations to prevent a RFPT high drain level alarm. There is sufficient time following a RFP trip for operators to respond appropriately. Even though there is a minimal increase in the probability of the loss of the second RFP due to high drain level following a single RFP trip, the event would simply become the loss of all feed flow transient described in the Updated Final Safety Analysis Report (UFSAR). A loss of all feed flow event is not a significant challenge to plant safety.
Plant
References:
EC 76965
BSEP 14-0093 Enclosure 1 Page 15 of 18
Title:
Supplemental Diesel Generator System Installation Change Package Revision Evaluation Identification Number: Action Request 684822 Brief
Description:
The scope of this change is to revise the change package that will install the Supplemental Diesel Generator (DGS) System, which provides a commercial grade, non-safety related supplemental three phase AC power source capable of supplying any of the four 4.16 kV emergency buses, via the 4.16 kV Balance of Plant (BOP) bus circuit path.
Summary of 10 CFR 50.59 Evaluation:
The DGS System, which provides a commercial grade, non-safety related supplemental three phase AC power source capable of supplying any of the four 4.16 kV emergency buses, via the 4.16 kV BOP bus circuit path. It will supply power within one hour from the Station Blackout (SBO) event, with the capacity to bring the affected unit to cold shutdown. The revision to the change package adds BOP tuning of Digital Synchronizer and Load Controller (DSLC) and the removal of operator restrictions to leave electrical enclosure when closing the 4 kV breakers.
This concern and other concerns were shown to be less than a minimal increase based on similar protective relaying and Emergency Diesel Generator testing.
Plant
References:
EC 79694 12-FSAR-0024
BSEP 14-0093 Enclosure I Page 16 of 18
Title:
Revise Battery Maintenance Surveillance Tests (MST's) to Validate Voltage Evaluation Identification Number: Action Request 687993 Brief
Description:
The scope of this change is to update the DC System Load Calculation BNP-E-6.120 and revise the battery surveillance capacity tests for Unit 2.
Summary of 10 CFR 50.59 Evaluation:
The change will allow a higher voltage to be credited for equipment operation by verifying that the voltage during the first minute of the capacity tests are greater than those required for equipment operation. The change to the first minute load profile of the station battery service capacity tests and the modified performance capacity tests indirectly limits the amount of load that can be supported by the batteries. The station batteries and the DC system are designed to not require greater than 916 Amperes during the first minute of a Design Basis Accident (DBA) concurrent with a loss of offsite power (LOOP). Therefore, reducing the one minute load limit to 725 Amperes adversely affects how the station batteries and the DC power system design function is performed and controlled. It was determined that this change maintains the design requirements of the facility as described in the Updated Final Safety Analysis Report (UFSAR).
Plant
References:
EC 95804
BSEP 14-0093 Enclosure 1 Page 17 of 18
Title:
Reactor Feed Pump (RFP) Rotating Assemblies and Diffusers Replacement Revision Evaluation Identification Number: Action Request 689425 Brief
Description:
This is a revision to REG AR 682472-02 to document a licensing review that was not performed in the original 50.59 evaluation.
Summary of 10 CFR 50.59 Evaluation:
Based on the evaluation, there are minimal increases in the frequency and likelihood of occurrence of Reactor Feed Pump Turbine (RFPT) damage due to high turbine condensate level in the operating turbine casing following a loss of a single RFP during near full power operation.
The increases are considered minimal because procedures are being revised to lower allowable reactor power during single pump operations to prevent a RFPT high drain level alarm. There is sufficient time following a RFP trip for operators to respond appropriately. Even though there is minimal increase in the probability of the loss of the second RFP due to high drain level following a single RFP trip, the event would simply become the loss of all feed flow transient described in the Updated Final Safety Analysis Report (UFSAR). A loss of all feed flow event is not a significant challenge to plant safety.
Plant
References:
EC 76965
BSEP 14-0093 Enclosure 1 Page 18 of 18
Title:
Supplemental Diesel Generator (DGS) Modification Testing Evaluation Identification Number: Action Request 691361 Brief
Description:
The scope of this change involves the non-safety related DGS output power (4KV) tying to existing Balance of Plant (BOP) 4KV buses for testing.
Summary of 10 CFR 50.59 Evaluation:
The use of this power during on-line testing and Digital Sequencer Load Control (DSLC) or Electro-Motive Diesel Electronic Controls (EMDEC) tuning represents a potential challenge to normal steady state operation by synchronizing another source of power to the bus or tuning changes while connected to plant buses. The 4KV BOP bus impact during monthly testing is the most significant nuclear safety concern. This concern and other concerns were shown to be less than a minimal increase based on similar protective relaying and Emergency Diesel Generator (EDG) testing that has been performed for the life of the plant. This provided the bases for a quantifiable probability.
Plant
References:
EC 79694 12FSAR-0024
BSEP 14-0093
BSEP 14-0093 Enclosure 2 Page 1 of 3 Regulatory Commitment Change Summary Report Table of Contents Activity Title Page Update License Renewal Commitments In NUREG- 1856, Appendix A 2
BSEP 14-0093 Enclosure 2 Page 2 of 3
Title:
Update License Renewal Commitments In NUREG-1856, Appendix A Originating Document: LDCR 13FSAR-037 Original Commitment:
The approval of the BNP License Renewal Application in June 2006 resulted in new commitments, aging management programs, and the incorporation of these changes into the Updated Final Safety Analysis Report (UFSAR). Consistent with the requirements of 10 CFR 54, a new UFSAR supplement was issued subsequent to the receipt of the renewed operating license as Chapter 18 under LDCR 06FSAR-027.
Revised Commitment:
The programs and commitments described in UFSAR Chapter 18 were required to be implemented prior to the period of extended operation, and the descriptions in Chapter 18 were written to be forward looking to reflect that these actions were pending. With BNP Unit 2 entering the period of extended operation in December 2014, it is necessary to update these program and commitment descriptions to reflect their current status, as implemented. This LDCR incorporates changes arising from License Renewal implementation into Chapter 18.
A description has been added of a new aging management program. The Compressed Air Monitoring Program has been implemented at BSEP based on operating experience (OE) and updated regulatory guidance.
UFSAR Chapters 9 and 18 are being revised to reflect that the Intake Structure Gantry Crane is being retired from service. This affects the description of the crane with regard to control of heavy loads in UFSAR 9. 1, the description of the Intake Structure in UFSAR 9.2, the description of Overhead Heavy Load and Light Load Handling Systems Program in UFSAR 18.1.9, and the deletion of the Time Limited Aging Analysis regarding crane load cycles in UFSAR 18.2.7.3.
Additional changes are made of an administrative or editorial nature. These include updating program descriptions to reflect current ASME Code Year and Addenda as approved under 10 CFR 50.55a, and to clarify instances where aging management requirements of one program are accomplished, in whole or in part, by activities prescribed by another.
Basis:
These changes did not affect the design function of any UFSAR-described Systems, Structures, and Components (SSCs). These revisions are generally associated with the implementation of License Renewal aging management programs and commitments, and represent the completion status of those activities.
With regard to administrative changes included in this revision, these are not of a scope or nature as to impact the design function or control of any UFSAR-described SSCs.
With regard to additional aging management activities being performed on the basis of OE or updated guidance, or are follow-up items arising from one-time inspection programs, these are
BSEP 14-0093 Enclosure 2 Page 3 of 3 non-intrusive inspection / monitoring activities that do not impact the control of any UFSAR described SSCs. This includes Fire Water System activities arising from the Selective Leaching Program, Preventive Maintenance Program activities arising from the One-Time Inspection Program, and the development of the new Compressed Air Monitoring Program.