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Results
Other: ML090330363, ML090770162, ML101160152, ML101160154, ML101160155, ML101160164, ML101160181, ML101160183, ML101160184, ML101160210, ML101160211, ML101160515
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MONTHYEARML0903304642009-01-28028 January 2009 Slides/Viewgraphs NRC Meeting - White Flint Regarding Browns Ferry Plant, Unit 1 Areva Fuel Transition Project stage: Meeting ML0903303632009-03-23023 March 2009 Loading Bleu Fuel in Browns Ferry, Unit 1 - Slides/Handouts - TVA Project stage: Other ML0907801812009-03-23023 March 2009 Summary of Meeting with the Tennessee Valley Authority Regarding Proposed Fuel Transition Amendment for Browns Ferry Nuclear Plant, Unit 1 Project stage: Meeting ML0907701622009-06-0303 June 2009 TVA, Presentation Slides for Browns Ferry, Unit 1 Project stage: Other ML0915205452009-06-0303 June 2009 Summary of Meeting with the Tennessee Valley Authority Regarding Proposed Fuel Transition Amendment Project stage: Meeting ML1011601542009-06-30030 June 2009 ANP-2821(NP), Revision 0, Browns Ferry Unit 1 Thermal-Hydraulic Design Report for ATRIUM-10 Fuel Assemblies (105% Oltp). Project stage: Other ML1011601522009-09-30030 September 2009 ANP-2859(NP), Revision 0, Browns Ferry Unit 1 Cycle 9 Fuel Cycle Design (105% Oltp). Project stage: Other ML1011602102009-10-0606 October 2009 51-9121503-002, Engineering Information Record, Responses to NRC Comments Regarding Browns Ferry Unit 1 Proposed Fuel Transition Amendment Project stage: Other ML1011605162009-10-31031 October 2009 Part 1: Previous NRC Requests for Additional Information Matrix and Text, Part 2: Browns Ferry Unit 1 - Summary of Response to Request for Additional Information, ANP-2860(NP), Rev. 2, Browns Ferry Unit 1 - Summary of Responses to Requests Project stage: Response to RAI ML1011605152009-10-31031 October 2009 ANP-2638NP, Revision 2, Applicability of Areva Np BWR Methods to Extended Power Uprate Conditions. Project stage: Other ML1011601642009-11-30030 November 2009 ANP-2877NP, Revision 0, Mechanical Design Report for Browns Ferry Unit 1 Reload BFR1-9 ATRIUM-10 Fuel Assemblies (105% Oltp). Project stage: Other ML0935613962009-12-23023 December 2009 Nonacceptance of Utilization of Areva Fuel and Associated Analysis Methodologies. (TAC ME2451) (TS-467) Project stage: Acceptance Review ML1011601812010-01-31031 January 2010 Gnf 0000-0111-8036-R0-NP, GE14 Fuel Thermal-Mechanical Information. Project stage: Other ML1011601842010-01-31031 January 2010 NEDO-32484, Revision 7, Browns Ferry Nuclear Plant Units 1, 2, and 3 SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis. Project stage: Other ML1005412492010-02-25025 February 2010 Withdrawal of an Amendment Request to Utilization of Areva Fuel and Associated Analysis Methodologies Project stage: Withdrawal ML1011601832010-03-31031 March 2010 ANP-2908(NP), Revision 0, Browns Ferry Units 1, 2, and 3 105% OLTP LOCA Break Spectrum Analysis. Project stage: Other ML1011601552010-03-31031 March 2010 ANP-2863(NP), Revision 1, Browns Ferry Unit 1 Cycle 9 Reload Safety Analysis for 105% Oltp. Project stage: Other ML1011602112010-03-31031 March 2010 ANP-2637, Revision 3, Boiling Water Reactor Licensing Methodology Compendium Project stage: Other ML1011602992010-04-16016 April 2010 Affidavit of Alan B. Meginnis Regarding Supplemental Information for Technical Specification Change TS-473 - Areva Fuel Transition Amendment Request Project stage: Supplement ML1011601532010-04-16016 April 2010 Supplemental Information for Technical Specification Change TS-473 - Areva Fuel Transition Amendment Request Project stage: Supplement ML1011601852010-04-30030 April 2010 NEDO-32484, Supplement 1, Revision 0, Browns Ferry Nuclear Plant Unit 1 Supplementary Report Regarding ECCS-LOCA Additional Single Failure Evaluation at Current Licensed Thermal Power. Project stage: Supplement 2009-06-03
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Category:Slides and Viewgraphs
MONTHYEARML24284A0042024-10-16016 October 2024 Application to Use Online Monitoring Methodology for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant Session Slides ML24228A2312024-08-15015 August 2024 TVA Meeting Slides for August 19 Public Meeting Re QAPD Supplement ML24184B9162024-07-10010 July 2024 U.S. NRC Meeting Slides for Meeting with Tennessee Valley Authority Regarding NRC Questions Regarding Scope of Nuclear Quality Assurance Program ML24149A1332024-05-29029 May 2024 Pre-Submittal Meeting for Proposed License Amendment Regarding Hydrologic Analysis Updates Public Portion Meeting Slides ML24113A0962024-04-22022 April 2024 RIPE Pre-Submittal Meeting Slides ML24078A2722024-04-10010 April 2024 Subsequent License Renewal Public Scoping Meeting ML24067A2832024-03-27027 March 2024 2023 Browns Ferry, Sequoyah and Watts Bar Annual Assessment Public Meeting Presentation Slides ML24032A2752024-02-0707 February 2024 Pre-Pre-Submittal Meeting for Proposed License Amendment Regarding Hydrologic Analysis Updates (Slides) ML24019A1512024-01-22022 January 2024 Slides - Modification of Browns Ferry Technical Specifications to Eliminate LCO 3.3.2.1 Actions C.2.1.1 and C.2.1.2 for Rod Worth ML23130A0912023-05-11011 May 2023 TVA Browns Ferry Nuclear Plant Safety Pre-Application Public Meeting Slides 05/11/2023 ML23130A0332023-05-11011 May 2023 NRC Presentation Browns Ferry Subsequent License Renewal Pre-application Meeting, Environmental Overview ML23130A0922023-05-11011 May 2023 NRC Browns Ferry Nuclear Plant, Units 1, 2, and 3, Subsequent License Renewal Application, Public Meeting Slides ML23130A0302023-05-10010 May 2023 TVA Presentation Browns Ferry Nuclear Plant Subsequent License Renewal License Application – Environmental Report ML23128A2882023-05-0808 May 2023 TVA Nuclear Plants -2022 EOC Media Slides ML23025A0472023-01-25025 January 2023 Pre-Submittal Meeting for Proposed License Amendment Request Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves - January 25, 2023 ML22285A1902022-10-13013 October 2022 October 13, 2022 Public Meeting on 5th Interval Alternative Planned Requests - Licensee Slides ML22277A6562022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October, 2022 (TVA Slides) ML22279A8992022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October 6, 2022-TVA Slides ML22264A2332022-09-22022 September 2022 Slides for Pre-Submittal Meeting for Request to Use a Later Edition of the ASME OM Code for the Fifth Inservice Testing (IST) 10-Year Interval ML22080A1662022-03-21021 March 2022 TVA Nuclear Plants -2021 EOC Media Loop Slides for Automatic Play ML21281A2282021-10-13013 October 2021 Tennessee Valley Authority Fleet Pre-Submittal Meeting for License Amendment Request to Change Emergency Action Level Scheme Presentation - October 13, 2021 (EPID L-2021-LRM-0096) (Slides) ML21270A0322021-09-27027 September 2021 Presentation Slides for Browns Ferry Pre-submittal Public Meeting September 27, 2021 ML21265A0422021-09-21021 September 2021 Presentation Slides for Browns Ferry Pre-submittal Public Meeting 09/22/2021 ML21250A3012021-09-0707 September 2021 TVA Slides for September 7, 2021, Presubmittal Meeting to Discuss Planned Browns Ferry TSTF-505 License Amendment Request ML21152A1872021-06-0101 June 2021 TVA Slides for June 1, 2021, Presubmittal Meeting to Discuss Planned Control Bay Chiller Cross-Tie License Amendment Request ML21096A1002021-04-0606 April 2021 Annual Assessments ML20175A0552020-06-23023 June 2020 TVA Slides for June 23, 2020, Emergency Plan Change Presubmittal Meeting ML20156A2812020-06-0808 June 2020 TVA Slides for June 8, 2020, ATRIUM-11 Presubmittal Meeting ML20112F5302020-04-21021 April 2020 TVA Nuclear Plants -2019 EOC Media Loop Slides for Automatic Play (Final) ML20092F5742020-04-0202 April 2020 TVA Slides for Browns Ferry 50.69 License Amendment Request Presubmittal Meeting ML20049G1822020-02-18018 February 2020 February 20, 2020 - Pre-submittal Meeting Presentation - Transition to Westinghouse Fuel ML20022A0262020-01-22022 January 2020 NEI Presentation Status Update for Ropte Short Term Action Plan: Removed Planned Unavailability for Mitigating Systems Performance Index ML19120A3692019-04-30030 April 2019 Public Meeting Summary - Browns Nuclear Plant, Docket No. 50-259, 50-260, and 50-296 ML18255A0142018-09-12012 September 2018 BWROG Presentation Slides for Public Meeting Sept 12 2018 ML18158A2862018-06-0707 June 2018 May 30, 2018 Summary of Public Meeting with Browns Ferry Nuclear Plant, Docket No. 50-259, 50-260, and 50-296 ML17271A0162017-09-28028 September 2017 Meeting Slide for Tennessee Valley Authority (TVA) Hydrology Precipitation Model Topical Report Review Status ML17212A8432017-08-0101 August 2017 Meeting Slides for Pre-submittal Meeting with Tennessee Valley Authority on Unbalanced Voltage License Amendment Request for TVA Nuclear Plants ML17034A3322017-02-0303 February 2017 Presentation Slides for Public Meeting Regarding Browns Ferry Extended Power Uprate License Amendment Request Transmission System Update Supplements ML16356A0342017-01-0404 January 2017 Pre-app Meeting Mellla+ LAR Final ML16341A7422017-01-0404 January 2017 Presentation Slides for Browns Ferry Pre-application Meeting Regarding Mellla+ ML16279A2332016-10-0505 October 2016 Summary of Closed Pre-Decisional Enforcement Conference with Tennessee Valley Authority Regarding Browns Ferry Nuclear Plant ML16189A3482016-07-19019 July 2016 Presentation Slides for July 19, 2016, Public Meeting ML16200A2592016-07-19019 July 2016 July 19, 2016: NRC Public Meeting on Browns Ferry Nuclear Plant Extended Power Uprate License Amendment Request ML16153A1982016-06-0101 June 2016 2015 EOC Meeting Summary ML16028A0962016-02-0101 February 2016 Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal Logic, and Unit Priority Re-Trip Logic License Amendment Request ML16006A2882016-01-0606 January 2016 Significant Operational Experience: 7 Major Industry Events with Regulatory Implications ML15308A1002015-11-10010 November 2015 Public Meeting Presentation Slides Extended Power Uprate License Amendment Request NRC Public Meeting ML15293A4582015-07-14014 July 2015 Slides for July 14, 2015 Public Meeting on Browns Ferry Seismic Risk Evaluations (MF3764 Through MF3766) ML15195A1252015-07-14014 July 2015 July 14, 2015 - Public Meeting Slides on Browns Ferry Seismic Risk Insights CNL-15-122, Presentation Slides for Closed Meeting Extended Power Uprate (EPU) License Amendment Request2015-07-0808 July 2015 Presentation Slides for Closed Meeting Extended Power Uprate (EPU) License Amendment Request 2024-08-15
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Text
R VAn 161
- In 1997, the Tennessee Valley Authority agreed to take from the Department of Energy over 30 metric tons of highly enriched uranium (HEU) to be converted to blended, low enriched uranium (BLEU) for use as fuel.
AREVA and TVA entered into an agreement for AREVA to provide this BLEU material in ATRIUMTM-10* BWR fuel assemblies for Browns Ferry Units 2 and 3.
4AREVA and TVA modified the agreement in 2008, adding Browns Ferry Unit 1 as another unit loading BLEU fuel.
- In April 2005, TVA reached a key milestone by loading its first reload of BLEU fuel into Browns Ferry Unit 2.
" AREVA has manufactured 1238 BLEU ATRIUM-10 assemblies that have been loaded and operated at Browns Ferry Units 2 and 3.
4 The Unit 1 transition will benefit from the experience already gained transitioning at Units 2 and 3.
" A dominant characteristic of BLEU is a high U234 and, U236 content compared to commercial grade uranium (CGU).
ATRIUM is a trademark of AREVA NP
- Material Process HEU is downblended to low-enriched aqueous uranyl nitrate, then converted to uranium oxide powder.
AREVA processes this into U0 2 pellets and loads them into BWR fuel assemblies.
Off-Spec HEU Irradiate in TVA Reactors Type I Ap Solutions Irradiated Fuel I. MIN&
Savannah River I Type II H Canyon Fuel Assemblies (Purify and down I
~ Unirradiated blend to LEU)
Fuel LEUN BLEU NFS BLEU Conversion Oxide Fuel Fabrication BLEU Preparation Complex Facility Facility (AREVA) , (AREVA) I Type II (Purify and down blend to LEUN)
% Ingots Richland, WA Highly Enriched Type III Uranium Erwin, TN
- Material Process HEU is downblended to low-enriched aqueous uranyl nitrate, then converted to uranium oxide powder.
AREVA processes this into U0 2 pellets and loads them into BWR fuel assemblies.
17 Tons Savannah River H Canyon Ecirwin, TN 16 Tons NFS Processing Facility Areid
- e Conversion F
" Solutions Store, Downblend NEU OxlC
~chland, WA
!Pelletize
- e,Pelletize UO, Irradiated in TVA Reactors
4Material Characteristics BLEU material meets the CGU specification with the exception of the isotopes U232, U 2 3 4 , and U 2 36.
Characteristics of Blended, Low-Enriched Uranium (BLEU)
Commercial Blended, Parameter Grade Low-Enriched CoIInUnt Uranium Uranium (CGU) (BLEU)
Within fuel fabrication Chemically Same as CGU process isotopes are inseparable from BLEU feed.
U235 Enrichment Effective Limit, wtU235 4.95 4.95 Fuel Fabrication plant limit.
234 U wt% 0.05 (ASTM 0.07 -1.4 times the ASTM (in 4.95 wt% U235 BLEU) limit) limit U2 36 wt% 0.025 (ASTM 1.5 -60 times the ASTM limit (in 4.95 wt% U235 BLEU) limit)
The impact of the U234, and U236 isotopes is to decrease reactivity due primarily to the absorption of neutrons by the U236.
In236 CGU at fuel burnups beyond 25 GWd/MTU there is a buildup of U concentrations of about one-third of those expected in BLEU.
a.
BLEU Lattice Equivalent CGU Lattice 4.24 wt% U235 Average Enrichment 3.95 wt% U235 Average Enrichment 1.20 -----------------------------------------------
1.15 ATRIUM-10 Lattice with BLEU (4.24 wt%)
N,\, ..... ATRIUM-10 Lattice with CGU (3.95 wt%)
1.10 --- ATRIUM-10 Lattice with CGU (4.24 wt%)
I N
N 1.05 Ný N 14.24 wt% Lattice with no BLEU I j i 411.00o
.* 0.95 'GU 0.90 0.85 0.80 0.75 -----------------------------------------------. - - - . .. . . .. . . ..------------------------
0 10 20 30 40 50 60 70 Lattice Exposure, GWd/MTU CGU and BLEU ATRIUM-10 Fuel Hot Operating, Uncontrolled, 40% Voids, k-infinity versus Exposure
- AREVA analytical methods employ the NRC-approved CASMO-4/MICROBURN-B2 3-D core simulator and lattice code.
4Parallel Unit 2 Cycle 14 calculations were performed - one utilizing CGU material and one with BLEU material.
- When explicitly accounting for the higher U234/U 236 content, a comparison of key core reactivity characteristics shows that core response will not be significantly different between BLEU and CGU cores.
Kinetic Parameters Comparison Br w er 2Cce1 Caclae Cor Avrg Paaee TRUM1 ATIU -1 wi G - wtBE e E OC Doppler Reactivity Coefficient, Ak/k/ 0 F -1.3 x 10- -1.4x i0-BOG Delayed Neutron Friction, .. 0.2 eff 0.0053 0.0052 EOC Control Rod SCRAM Worth, Ak/k -0.22 -0.22 BOG Void Reactivity Coefficient,
... ... Ak'V A:%/k/i< VO.
F
-0 "l__l-0.10
Browns Ferry Units 213 Transitioned to AREVA ATRIUM-10 BWR Fuel Design Key Core Design Parameters Reactr-Brwns Ferry Reactor-Browns erry 764 Assemblies BWR/4, D-Lattice, Planned 120% uprates 2/3 345 AmWi, 3458 MWt, 511tokW/1 3952 MWt, 58.5 kW/1 Fuel type/co-resident ATRIUM- 10 BLEU fuel GE- 13/-14 Loading Strategy Scatter load Cycle Length, months 24 Browns Ferry Unit I to Transition to AREVA ATRIUM-10 BWR Fuel Design Key Core Design Parameters Reactor-Browns Ferry BWR/4, D-Lattice, Same as planned uprates Unit 1 at Units 2 and 3 3952 MWt, 58.5 kW/l Fuel type/co-resident ATRIUM-10 BLEU Same as Units 2/3 fuel GE- 13/-14 experience Same as Units 2/3 Loading Strategy Scatter load experience experience Same as Units 2/3 Cycle Length, months 24 experience experience
LI BLEU Operating Experience-- Cycles Completed Unt3Uit2Ui Paramete Cycle Length, EFPD 699 (2,417) 669 (2,312) 694 (2,400)
(GWd)
Reload Fuel Type ATRIUM-10 ATRIUM-10 ATRIUM-10 Fuel Material Type CGU BLEU BLEU Batch Average 3.82 3.92 4.17 Enrichment, % U-235 Reload Batch Size 300 (39%) 280 (37%) 296 (39%)
Predicted BOC Cold Shutdown Margin, %Ak/k Measured BOC Cold Shutdown Margin, %Ak/k BLEU Operating Experience - Currently Operating Unit 2Unit Cycle Length, EFPD 779 (2,693) 652 (2,254)
(GWd)
Reload Fuel Type ATRIUM- 10 ATRIUM- 10 Fuel Material Type BLEU BLEU Batch Average 4.13 4.22 Enrichment, % U-235 Reload Batch Size 374 (49%) 288 (38%)
Predicted BOC Cold Shutdown Margin, %Ak/k Measured BOC Cold Shutdown Margin, %Ak/k
cm.6-0 ALI 1.010
+Uni2 Cycle 14- BLEU XUnit3 Cycle 13- BLEUt
+ Unit 2 Cycle 15- BLEU
-Unit3 Cycle 14-BLEU 1.005 1.000 0.995 Range ofCASMO-4/MICROBURN-B2 calculated k-effective experience 0.990 0.0 2.0 4.0 6.0 8.0 10.0 12.0 14.0 16.0 18.0 20.0 Cycle Exposure (GWd/MTU)
Comparison of Calculated Browns Ferry 2/3 BLEU k-effectives with Other CASMO-4/MICROBURN-B2 Experience
0006song. AAMILL.
,qMMPw -011111P Few AdmlhL Twý-OW04MMOOMM Pre-BLEU (Cycle 13) BLEU (Cycle 14)
Browns Ferry Unit 2 Cycle 13 1076 MWd/MTU Browns Ferry Unit 2 Cycle 14 213 MWd/MTU
-Measured - - - Calculated - Measured - - Calculated 2.0 2.0 1 1.5 1.5
-1.0 0.5 0.5 0.0 0.0--------------
1 3 5 7 9 11 13 15 17 19 21 23 1 3 5 7 9 II 13 15 17 19 21 23 Bottom Axial Node Top Bottom Axial Node Top Browns Ferry Unit 2 Cycle 13 14605 MWd/MTU Browns Ferry Unit 2 Cycle 14 8804 MWd/MTU
-Measured - - - Calculated -Measured-- - Calculated 2.0 2.0 0 1.5
.- 1.0 0.5 05 z
0.0 0.0 1 3 5 7 9 11 13 15 17 19 21 23 1 3 5 7 9 I1 13 15 17 19 21 23 Bottom Axial Node Top Bottom Axial Node Top Browns Ferry Unit 2 Cycle 13 17276.98 MWd/MTU Browss Ferry Unit 2 Cycle 14 11590 MWd/MTU
- Measured - - - Calculated I - Measured - - Calculated 2.0 2.0 1.5 1.5
.- 1.0 j0.50.5 0.5 z
0.0 0.0 3 5 7 9 11 13 15 17 19 21 23 1 3 5 7 9 11 13 15 17 19 21 23 Bottom Axial Node Top Bottom Axial Node Top
B AmKlhb an IMLAW
'w omnem BLEU (Cycle 15)
B.F.,U 2 Cy*e 15 74,AVDAST
-- ~~ ~~ -- - -- - -- - -
1.4-1.0.
1'i o 1,2 14 i. 2 i 41 1.4 2 4 0 a 12 12 14 10 10 20 22 24 B~*O Fen~UM02 Cjo 1 16713.25 MWVMW 2-M, 1.t 1.2
'U OA ao~
CS**0" C-~I..W11d1 4.0 A-".hW31 9
tfýIll 4 0 1 Op
Pre-BLEU (Cycle 12) BLEU (Cycle 13)
Browns Ferry Unit 3 Cycle 12 879 MWd/MTU Browns Ferry Unit3 Cycle 13 153MWd/MTU
-Measured --- Calculated -Measured --- Calculated 2.0 2.0 S1.5 I- 1.0 1- 1.0
0.0 ..... --- 0.0 1 3 5 7 9 I1 13 15 17 19 21 23 I 3 5 7 9 II 13 15 17 19 21 23 Bottom Axial Node Top Bottom Axial Node Top Browns Ferry Unit 3 Cycle 12 9026 MWd/MTTU Browns Ferry Unit 3 Cycle 13 2672 MWd/MTU
-Measured --- Calculated - Measured Calculated 2.0 2.0 I
S1.5 4 1.5 1- 1.0 1-1.0 0.5 0.5 0.0 0.0 I 3 5 7 9 II 13 15 17 19 21 23 3 5 7 9 I1 13 15 17 19 21 23 Bottom Axial Node Top Bottom Axial Node Top i....P.FentlJa S 0I010 lhO1 4fleav*GdT Browns Ferry Unit 3 Cycle 12 15583 MWd/MTU
-Measured - - - Calculated 2.0 1.4 1.5
.1 1.0 o.e 0.5 *4 0.0 3 5 7 9 I1 13 15 17 19 21 23 Bottom Axial Node Top
BLEU (Cycle 14)
A lyU n l3 Cydb 14 ZA&41MWD /rM "
rw-iu CoMA84AWrAV BIwIIs Fe"y ArM3 C" 14 58447 MWDAIT f:-Mmd 2.01 1.I.
1.8.
1.4.
1.2.
S0.6-0.2.
24 8 8 10 12 14 18 is 2 22 24 bo~m Nod. wo Can AAd Avelug
- BLEU fuel has been successfully loaded and operated in TVA's Browns Ferry Units 2 and 3.
> Each unit has completed one complete cycle of operation with BLEU fuel and is currently in the second cycle.
The transition at Unit 1 will be similar to what has already been successfully done at Units 2 and 3.
- AREVA CASMO-4/MICROBURN-B2 neutronic modeling methodology very accurately models fuel behavior of BLEU fuel
> No significant differences are seen between BLEU and non-BLEU core designs.
> Initial reactor measured data are very good and consistent with prior cycle results.
--A