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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] |
Text
ENCLOSURE 6 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 2 TECHNICAL SPECIFICATIONS (TS) CHANGE TS-418 EXTENDED POWER UPRATE (EPU)
CDI TECHNICAL NOTE NO. 08-13NP, "LIMIT CURVE ANALYSIS WITH ACM REV. 4 FOR POWER ASCENSION AT BROWNS FERRY NUCLEAR UNIT 2," REVISION 1 (NON-PROPRIETARY VERSION)
Attached is the non-proprietary version of CDI Technical Note No. 08-13NP, "Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Browns Ferry Nuclear Unit 2."
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information C.D.I. Technical Note No. 08-13NP Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Browns Ferry Nuclear Unit 2 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 Alan J. Bilanin Prepared by Milton E. Teske May 2009
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Table of Contents Section, Page T able of C ontents ..................................................................... i
- 1. Introduction ............................................................................ 1
- 2. A pproach .............................................................................. 2
- 3. L im it C urves ........................................................................... 4 4 . References ............................................................................. 9
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information
- 1. Introduction During power ascension of Browns Ferry Nuclear Unit 2 (BFN2), from Current Licensed Thermal Power (CLTP) to Extended Power Uprate (EPU), TVA is required to monitor the dryer stresses at plant power levels that have not yet been achieved. Limit curves provide an upper bound safeguard against the potential for dryer stresses becoming higher than allowable, by estimating the not-to-be-exceeded main steam line pressure levels. In the case of BFN2, in-plant main steam line data have been analyzed at CLTP conditions (based on Unit 2 data) to provide steam dryer hydrodynamic loads [1]. EPU is 120% of Original Licensed Thermal Power (OLTP); CLTP is 105% of OLTP. A finite element model stress analysis has been undertaken on the CLTP loads [2]. These loads provide the basis for generation of the limit curves to be used during BFN2 power ascension.
Continuum Dynamics, Inc. (C.D.I.) has developed an acoustic circuit. methodology (ACM) that determines the relationship between main steam line data and pressure on the steam dryer [3]. This methodology and the use of a finite element model analysis provide the computational algorithm from which dryer stresses at distinct steam dryer locations can be tracked through power ascension. Limit curves allow TVA to limit dryer stress levels, by comparing the main steam line pressure readings - represented in Power Spectral Density (PSD) format - with the upper bound PSD derived from existing in-plant data.
This technical note summarizes the proposed approach that will be used to track the anticipated stress levels in the BFN2 steam dryer during power ascension, utilizing Rev. 4 of the ACM [4], and the options available to TVA should a limit curve be reached.
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information
- 2. Approach The limit curve analysis for BFN2, to be used during power ascension, is patterned after the approach followed by Entergy Vermont Yankee (VY) in its power uprate [5]. In the VY analysis, two levels of steam dryer performance criteria were described: (1) a Level 1 pressure level based on maintaining the ASME allowable alternating stress value on the dryer, and (2) a Level 2 pressure level based on maintaining 80% of the allowable alternating stress value on the dryer. The VY approach is summarized in [6].
To develop the limit curves for BFN2, the stress levels in the dryer were calculated for the current plant acoustic signature, at CLTP conditions, and then used to determine how much the acoustic signature could be increased while maintaining stress levels below the stress fatigue limit. During power ascension, strain gage data will be converted to pressure in PSD format at each of the eight main steam line locations, for comparison with the limit curves. The strain gage data will be monitored throughout power ascension to observe the onset of discrete peaks, if they occur.
The finite element analysis of in-plant CLTP data found a lowest alternating stress ratio of 3.20 [2] as summarized in Table 1. The minimum stress ratios include the model bias and uncertainties for specific frequency ranges as suggested by the NRC [7, 8]. The results of the ACM Rev. 4 analysis (based on Quad Cities Unit 2, or QC2, in-plant data) are summarized in Table 2 (a negative bias is conservative). The standpipe excitation frequency of the main steam safety relief valves in BFN2 is anticipated to be 111 Hz [9], and thus the uncertainty determined around the QC2 excitation frequency of 155 Hz has been applied to the 109 to 113 Hz frequency interval. Note also that it is anticipated that the 218 Hz will be mitigated by plugging the blank standpipes prior to power ascension, and that the stress analysis is based on this modification.
The additional bias and uncertainties, as identified in [10], [11], [12], [13], [14], and [15], are shown in Table 3. SRSS of the uncertainties, added to the ACM bias, results in the total uncertainties shown in Table 4. These uncertainties were applied to the finite element analysis, resulting in the minimum stress ratio of 3.20.
Table 1. Peak Stress Limit Summary for ACM Rev. 4 Peak Stress Limit 113,600 psi (Level 1) 10,880 psi (Level 2)
Minimum Stress Ratio 3.20 2.56 2
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Table 2. Bias and uncertainty for ACM Rev. 4 Er (3)))
Table 3. BFN2 additional uncertainties (with references cited)
Er (3)]1 Table 4. BFN2 total uncertainty Er (3)))
3
This Document Does. Not Contain Continuum Dynamics, Inc. Proprietary Information
- 3. Limit Curves Limit curves were generated from the in-plant CLTP strain gage data collected on Unit 2 and reported in [1]. These data were filtered across the frequency ranges shown in Table 5 to remove noise and extraneous signal content, as suggested in [16]. The resulting PSD curves for each of the eight strain gage locations were used to develop the limit curves, shown in Figures 1 to 4. Level 1 limit curves are found by multiplying the main steam line pressure traces by the limiting stress ratio (3.20), while the Level 2 limit curves are found by the same process, but with 80% of the limiting stress ratio (2.56). Note that for BFN2, low flow pressure signals are not removed from CLTP pressure signals. PSD results are then developed from the Level 1 and Level 2 pressure signals.
Consistent with the stress analysis [2], the peaks at 218 Hz on all eight strain gage signals were also filtered from the main steam line data prior to the development of the limit curves.
BFN2 intends to mitigate the effect of the eight blind standpipes on main steam lines A and D, prior to power ascension.
Table 3.2. Exclusion frequencies for BFN2 strain gage data, as suggested in [4]. VFD = variable frequency drive, CLTP. An
- indicates signals were truncated (exclusion filtering not applied).
CLTP Frequency Exclusion Interval (Hz) Cause 0-2 Mean 59.9- 60.1 Line Noise 119.9 - 120.1 Line Noise 179.9 - 180.1 Line Noise 239.9 - 240.1 Line Noise 44.7-46.0 VFD (lx) 90.8-91.0 VFD (2x) 136.1 - 136.5 VFD (3x) 181.6- 181.8 VFD (4x) 227.1 - 227.4 VFD (5x) 112.75 - 113.25
- Recirc Pump A Speed (5x) 110.75 - 111.25
- Recirc Pump B Speed (5x) 218.6 - 220.2 Blank Standpipe Excitation 4
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information
((I (3)))
Figure 1. Level I (black) and Level 2 (red) limit curves for main steam line A, compared against the base curves (blue) over the frequency range of interest: A upper strain gage location (top); A lower strain gage location (bottom).
5
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information (3)))
Figure 2. Level I (black) and Level 2 (red) limit curves for main steam line B, compared against the base curves (blue) over the frequency range of interest: B upper strain gage location (top); B lower strain gage location (bottom).
6
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information (3)))
Figure 3. Level I (black) and Level 2 (red) limit curves for main steam line C, compared against the base curves (blue) over the frequency range of interest: C upper strain gage location (top); C lower strain gage location (bottom).
7
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information rr (3)))
Figure 4. Level 1 (black) and Level 2 (red) limit curves for main steam line D, compared against the base curves (blue) over the frequency range of interest: D upper strain gage location (top); D lower strain gage location (bottom).
8
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information
- 4. References
- 1. Continuum Dynamics, Inc. 2008. Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Browns Ferry Nuclear Unit 2 Steam Dryer to 250 Hz (Rev. 4). C.D.I.
Report No. 08-05 (Proprietary).
- 2. Continuum Dynamics, Inc. 2009. Stress Assessment of Browns Ferry Nuclear Unit 2 Steam Dryer with Steam Dam, Outer Hood, and Tie-Bar Reinforcements (Rev. 0). C.D.I. Report No.
09-13 (Proprietary).
- 3. 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 (Proprietary).
- 4. Continuum Dynamics, Inc. 2007. Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, with the Inclusion of a Low Frequency Hydrodynamic Contribution (Rev. 1). C.D.I. Report No. 07-09 (Proprietary).
- 5. Entergy Nuclear Northeast. 2006. Entergy Vermont Yankee Steam Dryer Monitoring Plan (Rev. 4). Docket 50-271. No. BVY 06-056. Dated 29 June 2006.
- 6. State of Vermont Public Service' Board. 2006. Petition of Vermont Department of Public Service for an Investigation into the Reliability of the Steam Dryer and Resulting Performance of the Vermont Yankee Nuclear Power Station under Uprate Conditions.
Docket No. 7195. Hearings held 17-18 August 2006.
- 7. NRC Request for Additional Information on the Hope Creek Generating Station, Extended Power Uprate. 2007. TAC No. MD3002. RAI No. 14.67.
- 81. Continuum Dynamics, Inc. 2008. Flow-Induced Vibration in the Main Steam Lines at Browns Ferry Nuclear Units I and 2, With and Without Acoustic Side Branches, and Resulting Steam Dryer Loads (Rev. 0). C.D.I. Report No. 08-14 (Proprietary).
- 9. Structural Integrity Associates, Inc. 2006. Evaluation of Browns Ferry Unit 2 Strain Gage Uncertainty and Pressure Conversion Factors (Rev. 0). SIA Calculation Package No. BFN-I IQ-301.
- 10. Continuum Dynamics, Inc. 2005. Vermont Yankee Instrument Position Uncertainty. Letter Report Dated 01 August 2005.
- 11. 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 I and 2 Steam Dryers (Rev. 0). Document No. AM-21005-008.
9
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information
- 12. Continuum Dynamics, Inc. 2007. Finite Element Modeling Bias and Uncertainty Estimates Derived from the Hope Creek Unit 2 Dryer Shaker Test (Rev. 0). C.D.I. Report No. 07-27 (Proprietary).
- 13. NRC Request for Additional Information on the Hope Creek Generating Station, Extended Power Uprate. 2007. RAI No. 14.79.
- 14. NRC Request for Additional Information on the Hope Creek Generating Station, Extended Power Uprate. 2007. RAI No. 14.110.
- 15. NRC Request for Additional Information on the Browns Ferry Generating Station, Extended Power Uprate. 2009. RAI No. 204/168.
- 16. Structural Integrity Associates, Inc. 2006. Main Steam Line 100% CLTP Strain Data Transmission. SIA Letter Report No. GSZ-06-017.
10
ENCLOSURE 7 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 2 TECHNICAL SPECIFICATIONS (TS) CHANGE TS-418 EXTENDED POWER UPRATE (EPU)
CDI AFFIDAVIT Attached is the CDI affidavit for the proprietary information contained in Enclosures 1, 2, and 3.
cContinuum Dynamics, Inc.
(609) 538-0444 (609) 538-0464 fax 34 Lexington Avenue Ewing, NJ 08618-2302 AFFIDAVIT Re: C.D.I. Report No.09-13P "Stress Assessment of Browns Ferry Nuclear Unit 2 Steam Dryer with Steam Dam, Outer Hood and Tie-Bar Reinforcements,"
Revision 0 C.D.I. Report No.08-05P "Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Browns Ferry Nuclear Unit 2 Steam Dryer to 250 Hz," Revision 4; and C.D.I. Technical Note 08-13P "Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Browns Ferry Nuclear Unit 2," Revision 1 I, Alan J. Bilanin, being duly sworn, depose and state as follows:
- 1. I hold the position of President and Senior Associate of Continuum Dynamics, Inc. (hereinafter referred to as C.D.I.), and I am authorized to make the request for withholding from Public Record the Information contained in the documents described in Paragraph 2. This Affidavit is submitted to the Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 2.390(a)(4) based on the fact that the attached information consists of trade secret(s) of C.D.I. and that the NRC will receive the information from C.D.I. under privilege and in confidence.
- 2. The Information sought to be withheld, as transmitted to TVA Browns Ferry as attachments to C.D.I. Letter No. 09085 dated 18 June 2009, C.D.I. Report No.09-13P "Stress Assessment of Browns Ferry Nuclear Unit 2 Steam Dryer with Steam Dam, Outer Hood and Tie-Bar Reinforcements," Revision 0; C.D.I. Report No.08-05P "Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Browns Ferry Nuclear Unit 2 Steam Dryer to 250 Hz," Revision 4; and C.D.I. Technical Note 08-13P "Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Browns Ferry Nuclear Unit 2," Revision 1
- 3. The Information summarizes:
(a) a process or method, including supporting data and analysis, where prevention of its use by C.D.I.'s competitors without license from C.D.I. constitutes a competitive advantage over other companies; (b) Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product; (c) Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs 3(a), 3(b) and 3(c) above.
- 4. The Information has been held in confidence by C.D.I., its owner. The Information has consistently been held in confidence by C.D.I. and no public disclosure has been made and it is not available to the public. All disclosures to third parties, which have been limited, have been made pursuant to the terms and conditions contained in C.D.I.'s Nondisclosure Secrecy Agreement which must be fully executed prior to disclosure.
- 5. The Information is a type customarily held in confidence by C.D.I. and there is a rational basis therefore. The Information is a type, which C.D.I. considers trade secret and is held in confidence by C.D.I. because it constitutes a source of competitive advantage in the competition and performance of such work in the industry. Public disclosure of the Information is likely to cause substantial harm to C.D.I.'s competitive position and foreclose or reduce the availability of profit-making opportunities.
I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to be the best of my knowledge, information and belief Executed on this day of ----- 2009.
AlanJ*J Bilan Continuum Dynamics, Inc.
Subscribed and sworn before me this day: &1 z/* )
Eieen5.-urmei~fer -Notary Public EILEEN P. BURMEISTER NOTARY PUBLIC OF NEW JERSEY
-MY COMM. EXPIRES MAY 6, 2012