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Category:Report
MONTHYEARML23192A4472023-07-31031 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, Owners 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 ML21246A2942021-09-29029 September 2021 Enclosufinal Ea/Fonsi for Tva'S Initial and Updated Triennial Decommissioning Funding Plans for Browns Ferry Nuclear Plant ISFSIs ML21246A2952021-09-29029 September 2021 Memo to File 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, 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 ML15282A2402015-09-21021 September 2015 Startup Test Plan 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 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-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). 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, 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). 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, 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 2023-07-31
[Table view] Category:Technical
MONTHYEARML23192A4472023-07-31031 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) ML15282A2402015-09-21021 September 2015 Startup Test Plan ML15282A2392015-09-21021 September 2015 Flow Induced Vibration Analysis and Monitoring Program 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, Startup Test Plan2015-09-21021 September 2015 Browns Ferry, Units 1, 2, and 3, Startup Test Plan 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, 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 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-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-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-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 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 ML13276A0662013-08-31031 August 2013 ANP-3153(NP), Revision 0, Browns Ferry Units 1, 2, and 3 LOCA-ECCS Analysis MAPLHGR Limit for Atrium Tm 1OXM Fuel, Enclosure 8 2023-07-31
[Table view] |
Text
Tennessee Vali ey Authority Division of Water Control Plannin Engineering Laboratory Cj y1 Ej I
C NATURAL HEATING AND COOLING IN THE WHEELER RESERVOIR APPROACH TO THE BROWNS FERRY NUCLEAR PLANT g 5 f Browns Ferry Nuclear Plant Advance Report No. 23 i .1$
Prepared by William R. Waldrop Norris, Tennessee March 1975 Report No. 63-50
NATURAL HEATING AND COOLING IN THE WHEELER RESERVOIR APPROACH TO THE BROWNS FERRY NUCLEAR PLANT INTRODUCTION Tennessee River temperatures in the'icinity of the TVA Browns Ferry Nuclear Plant are monitored every quarter of an hour to assure com-pliance with the Alabama thermal water quality standards. These tempera-tures are recorded by five permanent floating monitors and telemetered to the plant for analysis. This report addresses the natural heating and cool-;
ing in the Wheeler Reservoir as the river'low approaches the plant.
PLANT FEATURES AND SITE DESCRIPTION Browns Ferry Nuclear Plant, now under construction, is located in north central Alabama on the north shore of Wheeler Reservoir at Tennessee River mile 294 as shown on Plate 1. When completed, the plant will contain three nu'clear-powered steam-electric generating units, each with a rated'.
capacity of 1152 megawatts.
During late 1973 unit 1 at the plant began operating with the con-denser cooling water system arranged in a once-through cooling mode. In this mode of operation heated water is passed directly from the steam condenser tnto Wheeler Reservoir through a 600-foot long diffuser pipe. The condenser flow is 1450 cubic feet per second, and the temperature rise across the condenser is 25'. The condenser cooling water pumping station is situated upstream from the powerhouse at the end of a short intake channel.
The cooling water diffuser system for the plant is constructed from perforated, corrugated, galvanized steel pipes laid side by side across the bottom of the main river channel. The diffuser location is shown by the map on Plate 2. The pipes are 17 feet, 19 feet, and 20 feet 6 inches in diameter and of different lengths as shown in detail on Plate 3. Each has the last 600 feet perforated on the downstream side with more than 7,000 holes two inches in diameter spaced six inches on centers in both directions.
The diffuser section for unit 1 occupies the center portion of the channel while unit 2 occupies the left-hand third, and unit 3 the right-hand third.
The topography of the reservoir at the site consists of a main navigation channel about 1,800 feet wide and 30 feet deep bordered by shallow overbank areas which vary from 2 to 10 feet in depth and 2,000 to 6,000 feet in width. A broad shallow area along the right bank (plant side) extends for several miles upstream.
HYDRO-THERMAL REGIME IN WHEELER RESERVOIR The hydraulic regime in the reservoir is controlled by the opera-tion of Guntersville (upstream) and Wheeler (downstr earn) Dams. These proj-'cts are operated primarily for hydro power production and navigation and at some periods of the year for flood control. Under present operating rules, the water level in Wheeler Reservoir does not vary more than six feet during the year. The mean annual flow in the Tennessee River at Browns Ferry is about 45,000 cubic feet per second; and the mean monthly average, estimated from the monthly averages at Guntersville Dam for the period 1959-1968, is presented in Plate 4.
Water temperatures in the reservoir have been monitored by perma-nent recording stations since the fall of 1968., Dates of initial operation of these monitors are listed in Table l. The natural water temperatures'n the reservoir range from about 40'. in the winter to a maximum (at the surface) of 85'-95'. in the summer with a maximum top to bottom vertical temperature difference of about 5'-8'.
At present, five temperature monitors are used to determine com-pliance of Bpowns Ferry Nuclear Plant with the Alabama State Water Tempera-ture Standards. The temperature of the heated discharge plume is determined by three stations (Nos. '9, 10, and 11) spaced across the reservoir at river mile 292.5. The plant receiving water temperature is determined by station (No. 6) at, river mile 309.7 or, if station 6 is inoperative, by station (No.
- 4) at mile 297.8. Plate 5 shows the location of these monitors. At 15-minute intervals a data logging system scans the stations and displays tem-perature data from the five-foot depth in the Browns Ferry control room to
ensure compliance with the state thermal standards. The monitoring system has been described in more detail in Reference l.
NATURAL HEATING AND COOLING UPSTREAt1 OF THE PLANT The river upstream of the monitor at Station 6, the primary monitor for determining the upstream temperature, may be described as riverine and generally confined to the natural river banks; consequently, velocities, are relatively h'igh between Guntersville Dam and Station 6. Slightly downstream of Station 6, the reservoir spreads over wide and shallow overbank regions.
Because of the large surface area along this stretch of the .reservoir, the heat flux to or from the atmosphere may be significant. During the spring and summer, the reservoir may warm considerably during daylight. hours. In the fall, the opposite is true and appreciable cooling of the reservoir may occu} along this overbank region. A qualitative description of this warming and cooling in the overbank region is shown in the aerial infrared imagery of Plates @ and 7N Plate 6r presents about a seven-mile stretch of the reservoir irrmediately downstream of Station 6. The lighter shades of gray indicate warmer surface water. Notice how the river tends to flow into the overbank area upstream and either warm or cool, depending upon the season.
, Plate 7; presents aerial infrared imagery of the right overbank region for about an eight-mile stretch of the reservoir immediately upstream .
of the plant. The same trend of warming or cooling continues until the flow along the overbank is mixed with the flow of the main channel in the vicinity of the plant.
Because of the large cross-sectional areas in the reservoir between
'tation 6 and Browns Ferry, the mean travel time is quite long. For instance, assuming a constant river flow of 35,000 cfs, 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> are required for a slug Reference 1: "tlonitoring of Mater Temperatures in Wheeler Reservoir to Determine Compliance of Browns Ferry Nuclear Plant with Water Temperature Standards." Advance Report No. 21. Tennessee Valley Authority, Division of Mater Control Planning, Engi-neering Laboratory.
of water to travel from Station 6 to Browns Ferry. This, of course, is based upon mean cross-sectional velocities. Considerable natural heating or cool-ing, possibly 4 F. or more, can occur during this time as is shown from the hourly recorded temperatures at Station 1 presented in Plates 8 and 9. This monitor is located nearest the plant and probably best reflects the natural river temperatures in the vicinity of the diffuser before operation of'he plant.
'A statistical analysis of the natural heating and cooling along this stretch of the reservoir has also been performed. The hourly differ-s ences between temperatures at the five-foot depth at Stations 1, 4, and 6 were analyzed on a monthly basis. Results of preplant operation are pre-sented in Plate 10 as'monthly mean values of hourly temperature differences and standard deviations about the mean. Recall that Station 1 is located furthest downstream and Station 6 is furthest upstream. This clearly indi-cates that during Hay 1973 the river warmed an average of 2'. between Station 6 and the plant and a natural warming of 3'. was not uncomnon.
The autumn cooling trend is also apparent in these results.
A similar analysis of the mean temperature differences between data from the five-foot depth of Stations 4 and 6 was performed. This com-parison covers a longer time span because both are upstream .of the plant and hence not influenced by the thermal discharge as was Station 1. The yearly cycle of heating and cooling is apparent in the results shown in Plate 11.
The spring heating during 1974 was apparently not as rapid as during 1973, but differences of 1.5'. between these two stations were not uncommon.
CONCLUSIONS TVA has positioned permanent floating monitors upstream and down-stream of the thermal di'scharge of the Browns Ferry Nuclear Plant to assess the incremental heating which the plant adds to the reservoir. The upstream monitor located 15 miles above the plant should determine the ambient temper-ature of the river before the thermal discharge. For several miles upstream of the plant, the 1/heeler Reservoir is very broad and often quite shallow.
As a result, mean velocities are low and overbank natural heating and cooling
is substantial during much of the year. After analyzing the available data which now spans several years, it is concluded that the upstream monitor at Station 6 is located too far upstream of the plant to provide reliable temperatures of the ambient river for assessing the incremental heating input of the plant.
TABLE 1 OPERATIONAL DATES OF BFNP RIVER TEMPERATURE MONITORS
. Monitor River flile . Ince tion Date 293.55 R Sept 1968 3 275. 0 L Dec 1968 297.78 L Sept 1969 285.25 R Sept 1969 309. 7 R Apr 1973
'7 295.7 R Sept 1973 294.5 L Sept 1973 9 292.5 R July 1973 10 ~
292. 5 L July 1973 292. 5 H July 1973
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TEMPERATURE PREDICTIONS SITE LOCATlON BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY DRAWN CvC w(C DIVISION OF WATER CONTROL PLANNING 03 KNGINEKRINO LABORATORY NoARI$ O-I5-72 67 cL 92 -A- I 08
600'
'600'0.5 600'9.0 CONCRETE
!7.0 'D l A DIA CULVERTS DIA I,450 cfs I,450 cfs UNIT 3 l,450 cfs UNIT I
~ UN IT 2 DIFFUSER APPROACH PIPE PLAN VlEW . BEGINNING OF
~
CORRUGATED PIPE CONDENSER HEAD = 4.5 FEET F L.OW OF WATER RlYER RI VER FLON F LOWt 2'IA {6) HOLES 5 6" O.C.
8- 0 SECT lON A "A 6 0 0 0 WATER TEMPERATURE SURVEY 0 0 0 0 GALVANIZED .STEEL PIPE 0 0 STRUCTURAL PLATE 0 0 DIFFUSER DESleN 2," DIA {7) HOLES+ -Q 0 0
'<3- GAGE, 2" x6" CORRUGATION M= 2l' = 5 6" O.C. BROWNS FERRY NUCLEAR PLANT ~
TEHNFSSKE VAt l EY AVTHORITY P
~ 24'a~ltg HOLE PATTERN O'YtStON OF WA<CR CONTROL R'wh '4 t~~EKAw'~t.Ag" a's~Mt D ETAILS
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JAN FE8 MAR APR MAY JUN. JUL AUG SEP OCT NOV DEC I959- l968 NATER TEMPERATURE SURVEY AVERAGE MONTHLY DISCHARGE GUNTERSVILLE DAM BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY Oll*wM C4QMCCA DIVISION OF WATER CONTROL PLANNINC Q 41/i gC/ 4 EIIOINKKRINO LABORATORY C+CCKCO AiMOYCO HCJK NoRRIs 3-5-75 67 r L 920 A-203
US'l I,65 RR~
Autumn Cooling US 31' Flow w
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s 4 wI~+ ll e Decatur, Ala. tlATER TEMPERATURE SURVEY Spring ffeating infrared. imagery Hear Decatur, Alabama MOINS FERRY NUCLEAR PLANT OWAWW TENNESSEE VALLEY AUTHORITY DIVISION OF WATER CONTROL PLANNING ENGlNEERING l.ABORATORY CwCCICO NBRRls q g 61 EL 92 A-305
Spring Heating Autumn Cool i ng Flow HATER TEMPERATURE SURVEY Infrared. Imagery Upstream of Brogans Ferry Nuclear Plant BROHNS FERRY NUCLEAR PLANT Ofl*WN TENNESSEE VALLEY AUTHORITY C NCIQN DIVISION OP WATER CONTROL PLANNING CNGINCCRING LABORATORY CaCChCD APJAOVCR B Js XCk N0RRls P-5-75 67 cL 92 A-206
2.0
-I . 0 AY JUN JLY AUG SEP OCT NOV DEC 5.0 2.0 0 1.0 0
~CD I- 0
-I.O
-2.0 MAY JUN JUL AUG SEP OCT NOV DEC COMPARISON OF MEAN MONTHLY TEMPERATURE DIFFERENCES AT THE FIVE-FOOT DEPTH OF STATIONS (I AND 4) AND (I AND 6) AT THE BROWNS WATER TEMPERATURE SURVEY FERRY NUCLEAR PLANT DURING I973.
TEMPERATURE DIF FERENCES STATIONS I-6 AND I-4'ROV!!NS
'FERRY NUCLEAR 'PLANT TENNESSEE VALLEY AUTHORITY Dg"m. DIVISION OF WATER CONTROL PLANNINC ENGINEERING LABORATOAY A1MOVCO FgO Noaws, 3-5-75 6? Ei 92 .A-209
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-I ~ 0 MAY JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SI P OCT NOV DEC 2.0 I 973 1974 COMPARISON OF MEAN MONTHLY TEMPERATURE AT THE FIVE-FOOT .DEPTH OF STATIONS 4 AND 6 AT THE BROWNS WATER TEMPERATURE S U R VE Y FERRY NUCLEAR'LANT TEMPERATURE DIFFERENCES STATIONS 4-6 BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY
~Crit DIVISION Oj WATER CONTROL PLANNING KN.
CeCCICO gC ktPAOVCO fNGINCERING LAGORATGRY 8 JG. GEO NoRRls 3 5 75 67 cI. 92 A-2 I 0