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Category:Report
MONTHYEARML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information ML23025A0752023-01-25025 January 2023 American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle . ML22363A3922022-12-28028 December 2022 Cycle 14 Mellla+ Eigenvalue Tracking Data CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval2022-12-12012 December 2022 Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval CNL-22-100, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information ML22154A4042022-06-0303 June 2022 Unit 3 Cycle 20 Mellla+ Eigenvalue Tracking Data CNL-22-057, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use2022-05-27027 May 2022 To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use ML21277A1232021-10-0404 October 2021 Submittal of Browns Ferry Unit 2 Reactor Pressure Vessel Vertical Weld Flaw Evaluation ML21246A2952021-09-29029 September 2021 Memo to File ML21246A2942021-09-29029 September 2021 Enclosufinal Ea/Fonsi for TVAs Initial and Updated Triennial Decommissioning Funding Plans for Browns Ferry Nuclear Plant ISFSIs CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User2020-12-16016 December 2020 10 CFR 71.95 Report for 3-60B Casks User ML20255A0002020-09-24024 September 2020 Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluated Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic ML20112F4852020-05-0606 May 2020 Staff Assessment of Flooding Focused Evaluation CNL-19-074, Extended Power Uprate - Flow Induced Vibration Summary Report2019-09-0404 September 2019 Extended Power Uprate - Flow Induced Vibration Summary Report CNL-19-004, Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2019-06-0707 June 2019 Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions CNL-19-041, Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report2019-04-16016 April 2019 Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report CNL-19-032, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information2019-03-13013 March 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report2018-11-29029 November 2018 Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report ML18283B5472018-10-10010 October 2018 Responding to Letter of 11/18/1977 from E. G. Case to G. Williams, Providing Environmental Qualification Information for Electrical Connectors in Reference of IE Bulletins 77-05 & 77-05A CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report2018-09-13013 September 2018 Extended Power Uprate - Flow Induced Vibration Summary Report CNL-18-060, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-05-31031 May 2018 Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ML18079B1402018-02-23023 February 2018 Browns Ferry Nuclear Plant, Units 1, 2, and 3: Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus ML17222A3282017-09-0505 September 2017 Flood Hazard Mitigation Strategies Assessment ML17170A0732017-06-15015 June 2017 Report Pursuant to 10 CFR 71.95 (a)(3) and (B) - Failure to Follow Conditions of TN-RAM Packaging Certificate of Compliance No. 9233 ML17114A3712017-04-20020 April 2017 Errata for BWRVIP-271NP: BWR Vessel and Internals Project, Testing and Evaluation of the Browns Ferry, Unit 2, 120 Degree Capsule ML17033B1642017-02-0202 February 2017 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement - Cycle 11 Operation Programs ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision2016-10-28028 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision ML16196A0882016-08-0505 August 2016 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation ML16146A0182016-05-25025 May 2016 Special Report 296/2016-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML16028A2952016-01-29029 January 2016 10 CFR 71.95 Notification Associated with the Failure to Observe Certificate of Compliance Condition of the 8-120B Secondary Lid Test Port Configuration ML16027A0592016-01-27027 January 2016 Snubbers Added to Lnservice Testing Program ML15356A6542015-12-22022 December 2015 Submittal of 10 CFR 50.46 30-Day Report CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)2015-09-25025 September 2015 Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) NL-15-169, Browns Ferry, Units 1, 2, and 3, Startup Test Plan2015-09-21021 September 2015 Browns Ferry, Units 1, 2, and 3, Startup Test Plan NL-15-169, Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 72015-09-21021 September 2015 Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 NL-15-169, Browns Ferry Units 1, 2 and 3, Flow Induced Vibration Analysis and Monitoring Program2015-09-21021 September 2015 Browns Ferry Units 1, 2 and 3, Flow Induced Vibration Analysis and Monitoring Program ML15282A1812015-09-21021 September 2015 Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 ML15282A2402015-09-21021 September 2015 Startup Test Plan ML15282A2392015-09-21021 September 2015 Flow Induced Vibration Analysis and Monitoring Program ML15254A5432015-09-11011 September 2015 Submittal of 10 CFR 72.48 Changes, Tests, and Experiments, Biennial Summary Report Associated with the Independent Spent Fuel Storage Installation NL-15-169, ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu).2015-08-31031 August 2015 ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu). ML15282A2362015-08-31031 August 2015 NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis. ML15282A1822015-08-31031 August 2015 ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9 NL-15-169, ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu).2015-08-31031 August 2015 ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu). NL-15-169, NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis.2015-08-31031 August 2015 NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis. ML15282A1842015-08-31031 August 2015 ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu). 2024-06-26
[Table view] Category:Technical
MONTHYEARML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information ML22363A3922022-12-28028 December 2022 Cycle 14 Mellla+ Eigenvalue Tracking Data CNL-22-100, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information ML22154A4042022-06-0303 June 2022 Unit 3 Cycle 20 Mellla+ Eigenvalue Tracking Data CNL-22-057, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use2022-05-27027 May 2022 To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use ML21277A1232021-10-0404 October 2021 Submittal of Browns Ferry Unit 2 Reactor Pressure Vessel Vertical Weld Flaw Evaluation CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User2020-12-16016 December 2020 10 CFR 71.95 Report for 3-60B Casks User ML20255A0002020-09-24024 September 2020 Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluated Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic ML20112F4852020-05-0606 May 2020 Staff Assessment of Flooding Focused Evaluation CNL-19-074, Extended Power Uprate - Flow Induced Vibration Summary Report2019-09-0404 September 2019 Extended Power Uprate - Flow Induced Vibration Summary Report CNL-19-004, Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2019-06-0707 June 2019 Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions CNL-19-041, Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report2019-04-16016 April 2019 Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report CNL-19-032, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information2019-03-13013 March 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report2018-11-29029 November 2018 Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report ML18283B5472018-10-10010 October 2018 Responding to Letter of 11/18/1977 from E. G. Case to G. Williams, Providing Environmental Qualification Information for Electrical Connectors in Reference of IE Bulletins 77-05 & 77-05A CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report2018-09-13013 September 2018 Extended Power Uprate - Flow Induced Vibration Summary Report ML18079B1402018-02-23023 February 2018 Browns Ferry Nuclear Plant, Units 1, 2, and 3: Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus ML17222A3282017-09-0505 September 2017 Flood Hazard Mitigation Strategies Assessment ML17114A3712017-04-20020 April 2017 Errata for BWRVIP-271NP: BWR Vessel and Internals Project, Testing and Evaluation of the Browns Ferry, Unit 2, 120 Degree Capsule CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision2016-10-28028 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision ML16196A0882016-08-0505 August 2016 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation ML16027A0592016-01-27027 January 2016 Snubbers Added to Lnservice Testing Program CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)2015-09-25025 September 2015 Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) NL-15-169, Browns Ferry Units 1, 2 and 3, Flow Induced Vibration Analysis and Monitoring Program2015-09-21021 September 2015 Browns Ferry Units 1, 2 and 3, Flow Induced Vibration Analysis and Monitoring Program ML15282A1812015-09-21021 September 2015 Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 NL-15-169, Browns Ferry, Units 1, 2, and 3, Startup Test Plan2015-09-21021 September 2015 Browns Ferry, Units 1, 2, and 3, Startup Test Plan ML15282A2402015-09-21021 September 2015 Startup Test Plan NL-15-169, Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 72015-09-21021 September 2015 Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 ML15282A2392015-09-21021 September 2015 Flow Induced Vibration Analysis and Monitoring Program NL-15-169, ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu).2015-08-31031 August 2015 ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu). NL-15-169, ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu).2015-08-31031 August 2015 ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu). NL-15-169, ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 92015-08-31031 August 2015 ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9 ML15282A1822015-08-31031 August 2015 ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9 ML15282A2362015-08-31031 August 2015 NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis. ML15282A1842015-08-31031 August 2015 ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu). ML15282A1852015-08-31031 August 2015 ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu). NL-15-169, NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis.2015-08-31031 August 2015 NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis. CNL-15-143, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report2015-07-31031 July 2015 the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report CNL-15-085, Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical2015-06-0303 June 2015 Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical CNL-14-208, Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Pl2014-12-17017 December 2014 Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plan CNL-14-089, (Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492)2014-12-11011 December 2014 (Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492) 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 CNL-14-038, Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc2014-03-31031 March 2014 Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid ML14077A0952014-01-30030 January 2014 BWROG-TP-14-001, Rev. 0, Containment Accident Pressure Committee (344) Task 1 - Cfd Report and Combined Npshr Uncertainty for Browns Ferry/ Peach Bottom Cvic RHR Pumps, Attachment 8 ML14077A0902013-12-31031 December 2013 BWROG-TP-13-021, Rev. 0, Containment Accident Pressure Committee (344) Task 4 - Operation in Maximum Erosion Rate Zone (Cvic Pump), Attachment 11 ML13225A5412013-12-19019 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13338A6342013-12-18018 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Browns Ferry Nuclear Plant, Units 1, 2, and 3, TAC Nos.: MF0902, MF0903, and MF0904 ML13276A0642013-09-30030 September 2013 ANP-3248NP, Revision 1, Areva RAI Responses for Browns Ferry Atrium 10XM Fuel Transition, Enclosure 3 2024-06-26
[Table view] Category:Technical Specification
MONTHYEARML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-008, And Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 And Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) ML21335A0672021-11-26026 November 2021 Summary Report for 10 CFR 50.59 Evaluations, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and NRC Commitment Revisions ML24019A1192021-04-0808 April 2021 Technical Specification 3.1.6, Rod Pattern Control CNL-20-003, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516)2020-03-27027 March 2020 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516) CNL-19-010, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513)2019-01-25025 January 2019 Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513) CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays CNL-18-062, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, Supplement 12018-04-19019 April 2018 Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, Supplement 1 CNL-18-041, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)32018-03-16016 March 2018 Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)3 CNL-18-042, Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 12018-03-0707 March 2018 Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 1 ML18079B1402018-02-23023 February 2018 Browns Ferry Nuclear Plant, Units 1, 2, and 3: Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus ML18066A1202018-02-20020 February 2018 Summary Report for 10 CFR 50.59 Evaluations, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and NRC Commitment Revisions - Updated CNL-16-165, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change2016-10-31031 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change NL-16-165, Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificat2016-10-31031 October 2016 Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificati CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision2016-10-28028 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision CNL-16-109, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates2016-07-13013 July 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates CNL-16-077, for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information2016-04-27027 April 2016 for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information CNL-16-073, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 12, Responses to Requests for Additional Information2016-04-22022 April 2016 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 12, Responses to Requests for Additional Information CNL-15-240, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information2015-11-13013 November 2015 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information CNL-15-187, Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In..2015-09-25025 September 2015 Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In.. NL-15-169, Browns Ferry, Units 1, 2 and 3 - Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate2015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 1 of 22015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 1 of 2 NL-15-169, Browns Ferry, Units 1, 2 and 3 - License Amendment Request TS-505 Extended Power Uprate, Evaluation of Proposed Changes2015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - License Amendment Request TS-505 Extended Power Uprate, Evaluation of Proposed Changes NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 2 of 22015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 2 of 2 NL-15-169, Browns Ferry, Units 1, 2 and 3 - Retyped Proposed Technical Specifications Changes, Attachment 32015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Retyped Proposed Technical Specifications Changes, Attachment 3 NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Bases Markups, Attachment 42015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Bases Markups, Attachment 4 ML15282A1692015-09-21021 September 2015 Proposed Technical Specification Markups, Part 2 of 2 ML15282A1522015-09-21021 September 2015 Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate NL-15-169, Browns Ferry, Units 1, 2 and 3 - Retyped Technical Specifications Bases Changes, Attachment 52015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Retyped Technical Specifications Bases Changes, Attachment 5 ML15282A1802015-09-21021 September 2015 Retyped Technical Specifications Bases Changes, Attachment 5 ML15282A1782015-09-21021 September 2015 Retyped Proposed Technical Specifications Changes, Attachment 3 ML15282A1672015-09-21021 September 2015 License Amendment Request TS-505 Extended Power Uprate, Evaluation of Proposed Changes ML15282A1792015-09-21021 September 2015 Proposed Technical Specification Bases Markups, Attachment 4 ML15282A1662015-09-21021 September 2015 Proposed Technical Specification Markups, Part 1 of 2 CNL-15-002, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Saftey Limits (TS-499)2015-03-0606 March 2015 Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Saftey Limits (TS-499) CNL-14-166, Application to Revise Technical Specifications 3.3.6.1, Table 3.3.6.1-1, Function 5.g and Bases (BFN-TS-479)2015-02-17017 February 2015 Application to Revise Technical Specifications 3.3.6.1, Table 3.3.6.1-1, Function 5.g and Bases (BFN-TS-479) CNL-14-068, (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485)2015-01-29029 January 2015 (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485) ML12242A4772012-08-28028 August 2012 License Amendment Request to Change Technical Specifications to Delete References to Section XI of the ASME Code and Incorporate References to the ASME OM Code and Allow Application of 25 Percent Extension of Surveillance Intervals to Accel ML1106004082011-02-25025 February 2011 Technical Specification Change TS-429 - Deletion of Low Pressure Coolant Injection Motor-Generator Sets ML1032103342010-11-12012 November 2010 Revised Technical Specifications Change TS-468 - Request to Extend Completion Time for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, & 3D ML1024305282010-08-27027 August 2010 Technical Specifications Change TS-474 - Request to Add TS 3.7.3, Control Room Emergency Ventilation (Crev) System, Action to Address Two Crev Subsystems Inoperable Due to Inoperable Crev System High Efficiency Particulate ML1005507002010-02-18018 February 2010 Technical Specifications Change TS-468 - Request to Extend Completion Time for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, and 3D ML0933506552009-11-17017 November 2009 Technical Specification Change TS-467-S - Utilization of Areva Fuel & Associated Analysis Methodologies - Non EPU Supplement ML0930801582009-10-23023 October 2009 Technical Specification Change TS-467 - Utilization of Areva Fuel and Associated Analysis Methodologies ML0929503402009-10-20020 October 2009 License Amendment Request for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 - Browns Ferry TS Change 469; Sequoyah Change 09-04; and Watts Change 09-19 ML0922904712009-08-11011 August 2009 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Response to Round 25 - Request for Additional Information - SCVB-82 Through SCVB-86 and Replacement Documentation ML0921101192009-07-27027 July 2009 Technical Specifications Change 465 - Revision of Technical Specifications to Eliminate Unnecessary Water Local Leak Rate Tests 2023-03-10
[Table view] Category:Bases Change
MONTHYEARML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) ML21335A0672021-11-26026 November 2021 Summary Report for 10 CFR 50.59 Evaluations, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and NRC Commitment Revisions CNL-20-003, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516)2020-03-27027 March 2020 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516) CNL-19-010, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513)2019-01-25025 January 2019 Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513) CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays CNL-18-041, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)32018-03-16016 March 2018 Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)3 CNL-18-042, Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 12018-03-0707 March 2018 Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 1 ML18066A1202018-02-20020 February 2018 Summary Report for 10 CFR 50.59 Evaluations, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and NRC Commitment Revisions - Updated CNL-16-165, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change2016-10-31031 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change NL-16-165, Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificat2016-10-31031 October 2016 Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificati CNL-16-109, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates2016-07-13013 July 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates CNL-16-073, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 12, Responses to Requests for Additional Information2016-04-22022 April 2016 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 12, Responses to Requests for Additional Information CNL-15-240, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information2015-11-13013 November 2015 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information CNL-15-187, Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In..2015-09-25025 September 2015 Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In.. CNL-14-068, (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485)2015-01-29029 January 2015 (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485) ML1106004082011-02-25025 February 2011 Technical Specification Change TS-429 - Deletion of Low Pressure Coolant Injection Motor-Generator Sets ML1032103342010-11-12012 November 2010 Revised Technical Specifications Change TS-468 - Request to Extend Completion Time for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, & 3D ML1024305282010-08-27027 August 2010 Technical Specifications Change TS-474 - Request to Add TS 3.7.3, Control Room Emergency Ventilation (Crev) System, Action to Address Two Crev Subsystems Inoperable Due to Inoperable Crev System High Efficiency Particulate ML1005507002010-02-18018 February 2010 Technical Specifications Change TS-468 - Request to Extend Completion Time for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, and 3D ML0922904712009-08-11011 August 2009 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Response to Round 25 - Request for Additional Information - SCVB-82 Through SCVB-86 and Replacement Documentation ML0921101192009-07-27027 July 2009 Technical Specifications Change 465 - Revision of Technical Specifications to Eliminate Unnecessary Water Local Leak Rate Tests ML0915400152009-05-29029 May 2009 Technical Specifications Changes TS-418 and TS-431 - Extended Power Uprate (EPU) - Response to Round 24 Request for Additional Information (RAI) EMCB.209 Regarding Steam Dryer Analyses ML0912000642009-04-24024 April 2009 Technical Specifications Change 464 - Application for Technical Specification Improvement to Adopt Technical Specification Task Force TSTF-476, Rev. 1, Improved BPWS Control Rod Insertion Process ML0904402062009-02-0909 February 2009 Response for Additional Information Regarding - Technical Specifications (TS) Change 444 - Adoption of Changes to Standard Technical Specifications Under Technical Specification Task Force (Tstf). ML0836501092008-12-22022 December 2008 Technical Specifications Change 463-T, One-time Extension of Surveillance Requirements (Srs) ML0835306192008-12-15015 December 2008 Technical Specifications Change TS-431 - Extended Power Uprate - Response to Round 22 Request for Additional Information - Unit 1 Large Transient Testing (Ltt) - ML0829602272008-10-17017 October 2008 Technical Specifications Change TS-418 - Extended Power Uprate - Response to Round 21 Request for Additional Information on Channel Bow ML0723602632007-08-31031 August 2007 07-31NP, Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Browns Ferry, Unit 2 and 3, Revision 0 ML0723602622007-08-31031 August 2007 07-30NP, Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Browns Ferry, Unit 1, Revision 0 ML0721303752007-07-31031 July 2007 CDI Report No. 07-05NP, Revision 0, Finite Element Model for Stress Assessment of Browns Ferry, Unit 1, Steam Dryer to 250 Hz ML0721303822007-07-31031 July 2007 CDI Report No. 07-06NP, Revision 0, Finite Element Model for Stress Assessment of Browns Ferry, Unit 2 & 2 Steam Dryer to 250 Hz ML0721303862007-07-31031 July 2007 CDI Report No. 07-09NP, Revision 0, Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, with Inclusion of a Low Frequency Hydrodynamic Contribution ML0721304152007-07-31031 July 2007 CDI Report No. 07-11NP, Revision 0, Dynamics of BWR Steam Dryer Components ML0721304292007-07-31031 July 2007 C.D.I. Technical Memorandum No. 07-26NP, Revision 0, Comparison of Browns Ferry Unit 1 & Unit 2 Main Steam Line Strain Gage / Pressure Readings ML0721304012007-07-31031 July 2007 CDI Report No. 07-10NP, Revision 0, Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Browns Ferry, Unit 2, Steam Dryer to 250 Hz ML0710100922007-04-0606 April 2007 (BFN) - Unit 3 - Technical Specifications (TS) Change TS-460-T - Request for One-Time Extension of Allowed Outage Time (AOT) - Emergency Diesel Generator (EDG) 3D ML0706003392007-02-26026 February 2007 Technical Specifications (TS) Changes TS-431 and TS-418 Extended Power Uprate (EPU) - Response to Round 12 Request for Additional Information (RAI) ML0628602672006-10-0505 October 2006 Technical Specification Changes TS-431 and TS-418 - Extended Power Uprate - Response to Round 10 Request for Additional Information ML0627902302006-10-0303 October 2006 Technical Specifications Changes TS-431 and TS 418 - Extended Power Uprate - Steam Dryer Stress Report, Revision 4 ML0627901402006-10-0202 October 2006 Technical Specifications Change TS-443 - Request for Additional Information (RAI) Regarding Oscillation Power Range Monitor ML0629201562006-09-13013 September 2006 Rev 1 to Technical Specification, NPSH Transient Study RHR and Core Spray Pumps, E12.5.1296 ML0617803082006-06-15015 June 2006 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Response to Round 5 Request for Additional Information ML0625103852006-05-31031 May 2006 Enclosure 3, Browns Ferry, Units 1, 2 & 3 - CDI Report No. 05-28P, Rev 1, Bounding Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements. ML0613004432006-05-31031 May 2006 GE-NE-0000-0053-7413-R0-NP, Browns Ferry, Units 1, 2 & 3 Steam Dryer Stress, Dynamic and Fatigue Analyses for EPU Conditions. ML0613004412006-05-31031 May 2006 C.D.I. Report 06-11, Rev 1, Hydrodynamic Loads on Browns Ferry, Unit 1 Steam Dryer to 200 Hz. ML0613601482006-05-11011 May 2006 Supplemental Response to NRC Round 3 Request for Additional Information Related to Technical Specifications Change No. TS-418 - Extended Power Uprate Operation ML0613004362006-05-0505 May 2006 Transmittal of Browns Ferry, Units 1, 2 & 3 - Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Steam Dryer Stress Report ML0606203282006-02-28028 February 2006 Technical Specifications (TS) Change TS-431 - Response to Request for Additional Information SPSB-A.11 Regarding Extended Power Uprate - Credit for Net Positive Suction Head 2023-03-10
[Table view] |
Text
ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 TECHNICAL SPECIFICATIONS (TS) CHANGES TS-431 AND TS-418 -
EXTENDED POWER UPRATE (EPU) OPERATION - STEAM DRYER STRESS REPORT HYDRODYNAMIC LOADS ON BROWNS FERRY NUCLEAR UNIT 1 STEAM DRYER TO 200 HZ (NON-PROPRIETARY VERSION)
Attached is the Non-Proprietary Version of CDI Report No. 06-11, "Hydrodynamic Loads on Browns Ferry Nuclear Unit 1 Steam Dryer to 200 Hz," Revision 1.
This Document Does Not Contain General Electric Proprietary Information C.D.I. Report No. 06-11 Hydrodynamic Loads on Browns Ferry Nuclear Unit 1 Steam Dryer to 200 Hz Revision 1 Prepared by Continuum Dynamics, Inc.
34 Lexington Avenue Ewing, NJ 08618 Prepared under Purchase Order No. 00053157 for TVA / Browns Ferry Nuclear Plant Nuclear Plant Road, P. 0. Box 2000 PAB-2M Decatur, AL 35609 Approved by
( 624A ib.^Alan J. Bilanin
\ A May 2006
Executive Summary Measured pressure time-history data in the four main steam lines of an SMT model of Browns Ferry Nuclear Unit 1 (BFNI) are processed by a dynamic model of the steam delivery system to predict loads on the full-scale steam dryer. These measured data are first positioned on the four main steam lines, and then used to extract acoustic sources in the system. A validated acoustic circuit methodology is used to predict the fluctuating pressures anticipated across components of the steam dryer in the reactor vessel. This pressure loading was then provided for structural analysis to assess the structural adequacy of the steam dryer in BFNI. Rev 1 This effort provides BFN1 with a dryer dynamic load definition that comes directly from measured BFN1 SMT data and the application of a validated acoustic circuit methodology, at power levels where the pressure data were acquired.
Table of Contents Section Page Executive Summary .......................................................... . i Table of Contents ........................................................... ii I. Introduction ............................................................ 1 II. Modeling Considerations ........................................................... 2 2.1 Helmholtz Analysis ........................................................... 2 2.2 Acoustic Circuit Analysis . ................................................... 3 III. Input Pressure Data . ........................................................... 5 IV. Results................................................................................. 14 V. Error Analysis ............................ ............................... 23 VI. Conclusions........................................................................... 24 VII. References............................................................................. 25 Appendix A: SMT Dryer Comparisons ................... ........................ 26 11
I. Introduction In Spring 2005 Exelon installed new stream dryers into Quad Cities Unit 2 (QC2) and Quad Cities Unit 1. This replacement design, developed by General Electric, sought to improve dryer performance and overcome structural inadequacies identified on the original dryers, which had been in place for the last 30 years. As a means for confirming the adequacy of the steam dryer, the QC2 replacement dryer was instrumented with pressure sensors at 27 locations. These pressures formed the set of data used to validate the predictions of an acoustic circuit methodology under development by Continuum Dynamics, Inc. for several years [1]. One of the results of this benchmark exercise [2] confirmed the predictive ability of the acoustic circuit methodology for pressure loading across the dryer. This methodology, validated against the Rev 1 Exelon full scale data and identified as the Bounding Pressure model, is used in this effort.
This report applies this validated acoustic circuit methodology to the Browns Ferry Nuclear Unit 1 (BFN 1) steam dryer and main steam line geometry. SMT data obtained from the four main steam lines and the instrumented subscale dryer were used to predict pressure levels on the SMT dryer and to generate predictions of the pressure loading on the BFN1 full-scale dryer at two power levels, Original Licensed Thermal Power (OLTP) and Extended Power Uprate (EPU).
II.Modeling Considerations The acoustic circuit analysis of the BFN1 steam supply system is broken into two distinct analyses: a Helmholtz solution within the steam dome and an acoustic circuit analysis in the main steam lines. This section of the report highlights the two approaches taken here. These analyses are then coupled for an integrated solution.
2.1 Helmholtz Analysis A cross-section of the steam dome (and steam dryer) is shown below in Figure 2.1, with BFNI dimensions as shown [3]. The complex three-dimensional geometry is rendered onto a uniformly-spaced rectangular grid (with mesh spacing of approximately 1.5 inches to Rev 1 accommodate frequency from 0 to 200 Hz in full scale), and a solution, over the frequency range of interest, is obtained for the Helmholtz equation a82 p + 2 p +2a 2 p p=V2p+ 2 p=
ei e2 az a2 a2 where P is the pressure at a grid point, (ois frequency, and a is acoustic speed in steam.
i g
1- Nominal Water level
_ .0% ^
Figure 2.1. Cross-sectional description of the steam dome and dryer, with the BFNI dimensions of a' = 16.0 in, b = 16.0 in, c' = 24.0 in, c = 14.5 in, d = 17.5 in, e =
15.5 in, f = 74.0 in, g = 163.0 in, i = 97.5 in, j = 189.0 in, k = 121.0 in, and R =
125.7 in (dimensions deduced from [3] to within 1.5 inches).
2
This equation is solved for incremental frequencies from 0 to 200 Hz (full scale), subject to the boundary conditions dP
- =0 dn normal to all solid surfaces (the steam dome wall and interior and exterior surfaces of the dryer),
dP c0O
-dn -P dn a normal to the nominal water level surface, and unit pressure applied to one inlet to a main steam line and zero applied to the other three.
2.2 Acoustic Circuit Analysis The Helmholtz solution within the steam dome is coupled to an acoustic circuit solution in the main steam lines. Pulsation in a single-phase compressible medium, where acoustic wavelengths are long compared to transverse dimensions (directions perpendicular to the primary flow directions), lend themselves to application of the acoustic circuit methodology. If the analysis is restricted to frequencies below 200 Hz, acoustic wavelengths are approximately 8 feet in length and wavelengths are therefore long compared to most components of interest, such as branch junctions.
Acoustic circuit analysis divides the main steam lines into elements which are each characterized, as sketched in Figure 2.2, by a length L, a cross-sectional area A, a fluid mean density p, a fluid mean flow velocity U, and a fluid mean acoustic speed a.
- A - element cross-sectional area (A)
I 11 I- L 1.1 Figure 2.2. Schematic of an element in the acoustic circuit analysis, with length L and cross-sectional area A.
3
This Page Does Not Contain General Electric Proprietary Information Application of acoustic circuit methodology generates solutions for the fluctuating pressure Pn and velocity un in the nth element of the form Pn = [Ane InXn + Bneik2nXn i(Ot u - I(a + Un kln)A eiklnXn + (() +UUnk2n)Bne ik2nXn Jeict Pa2 kIn k2n where harmonic time dependence of the form el't has been assumed. The wave numbers kIn and k2 nare the two complex roots of the equation k n 22 +i n~I(÷~ z(+
o Unkn) n )-= 2 ((O +Un kn) nY~u)=0 Dna a where fn is the pipe friction factor for element n, Dn is the hydrodynamic diameter for element n, and i = Oh7 . An and B. are complex constants which are a function of frequency and are determined by satisfying continuity of pressure and mass conservation at element junctions.
The solution for pressure and velocity in the main steam lines is coupled to the Helmholtz solution for the steam dome, to predict the pressure loading on the steam dryer.
The main steam line piping geometry is summarized in Table 2.1.
Table 2.1. Main steam line lengths at BFN1, scaled from SMT lengths [4]. The main steam lines are 26 inch (ID = 24.0 in).
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This Page Does Not Contain General Electric Proprietary Information III. Input Pressure Data Microphones were mounted on the four main steam lines of the SMT, and at 18 locations on the surface of the SMT dryer. Two data sets, at Original Licensed Thermal Power (OLTP) and at Extended Power Uprate (EPU), were examined.
The main steam line pressure signals may be represented in two ways, by their minimum and maximum pressure levels, and by their PSDs as a function of frequency. Table 3.1 provides the pressure level information, while Figures 3.1 to 3.8 compare the OLTP and EPU frequency content at the eight measurement locations.
Table 3.1. Main steam line (MSL) pressure levels in the SMT for BFN1 [5].
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Figure 3.1. PSD comparison of pressure measurements on the SMT main steam line A at the upper microphone: OLTP (top) and EPU (bottom).
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(3)))1 Figure 3.2. PSD comparison of pressure measurements on the SMT main steam line A at the lower microphone: OLTP (top) and EPU (bottom).
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Figure 3.3. PSD comparison of pressure measurements on the SMT main steam line B at the upper microphone: OLTP (top) and EPU (bottom).
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Figure 3.4. PSD comparison of pressure measurements on the SMT main steam line B at the lower microphone: OLTP (top) and EPU (bottom).
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Figure 3.5. PSD comparison of pressure measurements on the SMT main steam line C at the upper microphone: OLTP (top) and EPU (bottom).
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(3)))j Figure 3.6. PSD comparison of pressure measurements on the SMT main steam line C at the lower microphone: OLTP (top) and EPU (bottom).
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Figure 3.7. PSD comparison of pressure measurements on the SMT main steam line D at the upper microphone: OLTP (top) and EPU (bottom).
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Figure 3.8. PSD comparison of pressure measurements on the SMT main steam line D at the lower microphone: OLTP (top) and EPU (bottom).
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This Page Does Not Contain General Electric Proprietary Information IV. Results The measured SMT main steam line pressure data were used to drive the validated acoustic circuit methodology for the BFN1 steam dome coupled to the main steam lines. Two calculations were undertaken at each power level provided.
- 1. A comparison was made between measured data on the subscale SMT dryer and predictions with the Bounded Pressure model [2] at subscale. These results are summarized in Figure 4.1, which illustrates the comparison between data and predictions for minimum and maximum pressures at the 18 microphone locations (identified in [6]
and [7]). Note that several of the microphones are located inside the dryer (Ml, M5, M8, Mll, M13, and M15) and several are on the 0°-180° centerline (M6, M7, M14, and Ml 5). Note also that the model predictions tend to match all SMT microphone data, with the exception of the 0°-1800 centerline data; it appears to be least effective in comparing against SMT data here, as the main steam line sources (located at 72°, 1080, 2520, and 2880) are farthest removed from these locations. However, it should be further noted that full-scale model comparisons on the QC2 steam dryer, at the pressure sensor closest to Rev 1 the 0°-1800 centerline (P17), shows no such under prediction [2]. It is suggested, therefore, that the SMT data may have overestimated the pressures in this region of the steam dryer, due in part to the use of a rigid steam-water boundary in SMT, and that the acoustic circuit analysis is more reasonable. Thus, no adjustment of predicted pressure at the 0°-180° region is necessary. Appendix A contains the PSD comparisons at the 18 microphones, in addition to a tabulation of the RMS comparison between predictions and measurements.
- 2. A prediction was made at full scale on the BFN1 dryer based on the scaling factors identified by GE [4, 5] and summarized in Table 4.1. A low resolution load, developed at the nodal locations identified in Figures 4.2 to 4.5, produces the maximum differential and RMS pressure levels across the dryer as shown in Figure 4.6. Since the highest loads are predicted on the surfaces of the outer bank hoods (and not on their edges), two sets of additional plots are shown in Figures 4.7 and 4.8 for the peak loads.
Table 4.1. Scaling factors used in converting SMT data to full scale.
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Figure 4.1. Maximum pressures measured and predicted at the 18 microphones on the SMT of the BFN1 dryer. Note the close agreement at microphones M2 and M3, and M9 and MIO, on the outside of the outer bank hoods opposite the main steam lines. The closed circles denote microphones positioned on the inside of the dryer, while the open circles denote microphones positioned along the 0°-180° dryer centerline.
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Figure 4.2. Bottom plates pressure node locations (low resolution), with pressures acting downward in the notation defined here.
16 cO I
r - -
3 4369
'3 17 411 197 15-z
II I
II Figure 4.4. Vertical plates: Pressures acting left to right on panels 6-11, 22-27, 38-43, and 50-54; acting right to left on panels 64-69, 80-85, and 94-99 (low resolution).
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F A Figure 4.5. Skirt plates: Pressure acting outward on the outer dryer 00/1800 surfaces and the skirt (low resolution).
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2 1-4 Cd
+-A r.-I (a.)49"
- _4 .'.O 1.5 0 Cn C4 a V
$_4 1 9 Cn Ln EV A-4 0.5 CI'd, 0
0 20 40 60 80 100 Node Number 0.6 0.5 Cn 0.4
- '-4 0.3 0.2 0.1 0
0 20 40 60 80 100 Node Number Figure 4.6. Predicted loads on the low resolution grid identified in Figures 4.2 to 4.5, as developed by the Bounding Pressure model, to 200 Hz. Low-numbered nodes are on the C-D side of the dryer, while high-numbered nodes are on the A-B side of the dryer.
20 C'0Y?3
4 3
"C 2 Cn C).4 1
U
- ..4
- Z V) 0 Cn (a.)
- __4 -1 A-4
-2
-3 0.5 1 1.5 2 2.5 3 3.5 Time (see) 1000 100 10 1
C:4 0.1 11/~
0.01 0.001 0.0001 0 50 100 150 200 Frequency (Hz)
Figure 4.7. Time history and PSD of the maximum high-resolution pressure loads predicted on the A-B side of the BFNI steam dryer at full scale. The behavior of the PSDs shown here, specifically below 125 Hz, is dependent on the conversion factors summarized in Table 4. 1.
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4 3 --- -- -- - - -- - - - - -- - - - - -- - -- --
2 ..... X]
0
-2
-4 0 0.5 1 1.5 2 2.5 3 3.5 Time (sec) 1000 I-100 --100 OLTP LT~oC-D on C- side ie---------- ---------------------- ---------- -
N EPU on C-D side
. 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -,-- - - - - - - -
A- - - - - - - - - - - - - - - - - - - - - - -----
C0.1 -- .. - -- ---- o 001 pH0.01 ---i- s a ' ' - -- -'-- ---' --- -----'--'--
0.0001 I,, I, I., , I 0 50 100 150 200 Frequency (Hz)
Figure 4.8. Time history and PSD of the maximum high-resolution pressure loads predicted on the C-D side of the BFN1 steam dryer at full scale. The behavior of the PSDs shown here, specifically below 125 Hz, is dependent on the conversion factors summarized in Table 4.1.
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V. Error Analysis The analysis of potential uncertainty occurring at BFN1 consists of several contributions, including the following: the uncertainty from using SMT data, the uncertainty from collecting data on the main steam lines at locations other than the locations on Quad Cities Unit 2 (QC2),
and the uncertainty in the Bounding Pressure model.
- 1. An uncertainty analysis of the SMT facility should be provided by GE.
- 2. An uncertainty analysis undertaken for Vermont Yankee [8] can be applied to the SMT data collection locations to estimate the location error of the main steam line microphones, as they were not located at their equivalent QC2 locations. That analysis would apply only to the SMT data, as TVA is expected to position their full scale data collection at the proper locations.
Scaling the position uncertainty discussed in [8] finds:
SMT Position Uncertainty 6.7%
- 3. An uncertainty analysis can be undertaken with regard to the Bounding Pressure model.
A comparison of the minimum and maximum pressures predicted at the external pressure transducers on QC2 (20 pressure transducers), compared to the minimum and maximum measured pressures, gives the following results:
Average Uncertainty -34.7%
One Standard Deviation 10.4%
Overall Uncertainty -24.3%
Thus, the Bounding Pressure model consistently over predicts the pressure levels measured on QC2 (including near the 0°- 1800 centerline), and no uncertainty need be applied to the results of the Bounding Pressure model as summarized in this report for BFN 1.
It should be noted that, through an extensive analysis, Exelon [9] concluded that the best estimate of the overall uncertainty for steam dryer acoustic circuit analysis methodology was that the error would range from a maximum under prediction of 3.5% to a maximum over prediction of 14.5%. These estimates are based on the use of strain gage pairs positioned on the four main steam lines at approximately 9.5 and 41.0 feet downstream of the steam dome. This analysis will be useful once TVA collects full scale data.
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VI. Conclusions The C.D.I. acoustic circuit analysis, using SMT measured data for BFN1:
a) Determines that steam dryer maximum differential pressure loads, based on the validated Bounding Pressure model, are about 2.2 psid (OLTP) and 3.6 psid (EPU), after Rev 1 converting subscale predictions to full scale.
b) Predicts that the loads on dryer components are largest for components nearest the main steam line inlets and decrease inward into the reactor vessel.
c) Determines that the validated Bounding Pressure model predicted pressures agree well with SMT data on the subscale dryer, with the exception being along the 0O-180° Rev 1 centerline, where the SMT data are believed to be conservative. This discrepancy is greatest on the skirt along the 0°-180° centerline and results from the fact that the acoustic circuit methodology incorporates acoustic radiation into the water between the skirt and the vessel. The acoustic circuit methodology predicts the QC2 skirt data conservatively and therefore it is believed that the SMT data is conservative on the skirt.
The following additional work is suggested:
- It is highly recommended that strain gages or pressure transducers be positioned at distances similar to those in Quad Cities Unit 2 (9.5 and 41.0 feet from the inside of the steam dome [2]), and that full scale data be collected and analyzed.
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VII. References
- 1. Continuum Dynamics, Inc. 2005. Methodology to Determine Unsteady Pressure Loading on Components in Reactor Steam Domes (Rev. 6). C.D.I. Report No. 04-09 (C.D.I. Proprietary).
- 2. Continuum Dynamics, Inc. 2005. Bounding Methodology to Predict Full Scall Steam Dryer Loads from In-Plant Measurements (Rev. 2). C.D.I. Report No. 05-28 (C.D.I. Proprietary).
- 3. Browns Ferry Unit 1 Drawings. 2006. Files: 729E229-I.tif, 729E229-2.tif, and 729E229-3.tif. BFN1 Email from G. Nelson dated 07 March 10:31:00 2006.
- 4. General Electric Energy, Nuclear. 2006. Transmittal of Updated Correction Factors for GE SMT BFNI Load Data. GE Letter No. GE-ERI-AEP-06-309.
- 5. General Electric Energy, Nuclear. 2006. Transmittal of GE Scale Model Testing Browns Ferry 1 Testing Data for CDI. GE Letter No. GE-ER1-AEP-06-304.
- 6. General Electric Energy, Nuclear. 2006. Revised BFNI Steam Dryer Sensor Locations and Steam Line Identification. GE Email from M. O'Connor dated 03 April 19:56:35 2006.
- 7. General Electric Energy, Nuclear. 2006. RE: Questions regarding Browns Ferry SMT Data.
GE Email from M. O'Connor dated 04 April 10:24:34 2006.
- 8. Continuum Dynamics, Inc. 2005. Vermont Yankee Instrument Position Uncertainty. Letter Report Dated 01 August 2005.
- 9. Exelon Nuclear Generating LLC. 2005. An Assessment of the Effects of Uncertainty in the Application of Acoustic Circuit Model Predictions to the Calculation of Stresses in the Replacement Quad Cities Units 1 and 2 Steam Dryers (Revision 0). Document No. AM-21005-008.
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This Page Does Not Contain General Electric Proprietary Information Appendix A: SMT Dryer Comparisons This appendix contains the comparisons between model predictions and pressure measurements on the SMT dryer, for both OLTP and EPU conditions. A comparison of RMS levels is given in Table A.1.
Table A. 1. Summary of RMS pressures at the two power levels examined.
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Figure A. 1. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone MI on the inside of the outer bank hood opposite main steam line C: OLTP (top) and EPU (bottom).
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Figure A.2. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M2 on the outside of the outer bank hood opposite main steam line C: OLTP (top) and EPU (bottom).
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Figure A.3. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M3 on the outside of the outer bank hood opposite main steam line D: OLTP (top) and EPU (bottom).
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Figure A.4. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M4 on the outside of the skirt between main steam lines C and D: OLTP (top) and EPU (bottom).
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Figure A.5. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M5 on the inside of the skirt between main steam lines C and D: OLTP (top) and EPU (bottom).
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Figure A.6. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M6 on the outside of the hood wall between main steam lines B and C: OLTP (top) and EPU (bottom).
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Figure A.7. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M7 on the outside of the skirt wall between main steam lines B and C: OLTP (top) and EPU (bottom).
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Figure A.8. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M8 on the inside of the skirt wall between main steam lines B and C: OLTP (top) and EPU (bottom).
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Figure A.9. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M9 on the outside of the outer bank hood opposite main steam line B: OLTP (top) and EPU (bottom).
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Figure A.10. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone MIO on the outside of the outer bank hood opposite main steam line A: OLTP (top) and EPU (bottom).
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Figure A. 11. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M 1I on the inside of the outer bank hood opposite main steam line A: OLTP (top) and EPU (bottom).
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Figure A.12. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M12 on the outside of the skirt between main steam lines A and B: OLTP (top) and EPU (bottom).
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Figure A.13. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M13 on the inside of the skirt between main steam lines A and B: OLTP (top) and EPU (bottom).
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Figure A.14. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M14 on the outside of the hood between main steam lines A and D: OLTP (top) and EPU (bottom).
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Figure A. 15. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M15 on the outside of the skirt between main steam lines A and D: OLTP (top) and EPU (bottom).
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Figure A.16. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M16 on the inside of the skirt between main steam lines A and D: OLTP (top) and EPU (bottom).
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Figure A.17. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M17 on the outside of the second bank hood opposite main steam line B: OLTP (top) and EPU (bottom).
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Figure A.18. PSD comparisons between SMT data for Browns Ferry and ACM predictions, for microphone M18 on the outside of the third bank hood opposite main steam line B: OLTP (top) and EPU (bottom).
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