ML093140266
| ML093140266 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/31/2009 |
| From: | Schnepp R AREVA NP |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| L32 090904 802, TS 467 EMF-2950(NP), Rev 0 | |
| Download: ML093140266 (155) | |
Text
{{#Wiki_filter:ATTACHMENT 15 ATTACHMENT Browns Ferry Nuclear Plant (BFN) Ferry Nuclear (BFN) Unit 1 Technical Specifications Technical Specifications (TS) Change Change 467 Revision Revi~ion of Technical Technical Specifications Specifications to allow utilization utilization of AREVA AREVA NP methodologies fuel and associated analysis methodologies LOCA Break Spectrum Spectrum Analysis Report Attached is the non-proprietary Attached non-proprietary version of the LOCA break spectrum analysis analysis report for for 120% OLTP conditions. 120%
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ISSUED IN ISSUED IN ON-UNE-DOCUMENT SYSTEM DOCUMENT SYSTEM AREVA NP Inc. DATE: 11/31 IJ /()'1 r ' EMF-2950(NP) Revision 0 Browns Ferry Units Units 1, 2, and 3 Extended Power Uprate Uprate Analysis LOCA Break Spectrum Analysis Prepared: R.R. R. R. Schnepp, Supervisor Date Thermal-Hydraulics Richland Thermal-Hydraulics Richland Reviewed: 9a-31e M.S. Stricker, Engineer Date Date Thermal-Hydraulics Richland Thermal-Hydraulics Richland Reviewed: A.B. Meginnis, Manager Manager r/3 1/;Jr Date Product Licensing Licensing Approved: Approved: ~n§. ..,.~~-- D.3Vrrd, Manager Date Date Thermal-Hydraulics Richland Thermal-Hydraulics Richland
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Customer Disclaimer Disclaimer Important Important Notice RegardingRegarding Contents Contents and Use of This Document Document PleaseRead Carefully Please Carefully AREVA NP, Inc.'s warranties and representations representations concerning concerning the subject matter matter of this document are those set forth in in the agreement agreement between between AREVA AREVA NP, Inc. and the Customer pursuant to which this document is issued. Accordingly, except as as otherwise expressly provided provided in in such agreement, neither AREVA NP, Inc. nor any person acting on its behalf:
- a. makes any warranty warranty or representation, express or implied, implied, with respect to thethe accuracy, completeness, or usefulness usefulness of the information information contained contained inin this this document, or that the use of any information, information, apparatus, apparatus, method, or process process disclosed in in this document document will not infringe infringe privately owned rights; or
- b. assumes any liabilities with respect to the use of, or for damages damages resulting resulting from the use of, any information, information, apparatus, method, or processprocess disclosed in in this document.
The information information contained contained herein is for the sole use of the Customer. In impairment of rights of AREVA NP, Inc. in In order to avoid impairment in patents or inventions inventions which may be included included in in the information information contained in in this document, the recipient, by its acceptance acceptance of this document, document, agrees not to publish or make public use (in (in the patent use of the term) of such information information until so authorized in writing by authorized in AREVA NP, Inc. or until after six (6) months following termination termination or expiration of the aforesaid Agreement Agreement and any extension extension thereof, unless expressly provided provided in in the Agreement. No rights or licenses in in or to any patents patents are implied by thethe furnishing of this document.
Browns Ferry Units browns Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Power Uprate Uprate Revision 0 Break Spectrum LOCA Break Analysis Spectrum Analysis Page Page ii Nature of Changes Changes This document document is the the* nonproprietary nonproprietary version document EMF-2950(P) of document Revision 2. EMF-2950{P) Revision The following items list the changes which were made in Revision 2 of EMF-2950(P): Item Page Description and Justification Description Justification 1.
- 1. All brackets for proprietary items.
Added brackets
- 2. 1-1, vi, 1-1, Removed statements Removed statements that CL TP was only applicable CLTP applicable for Units 2 and 3 4-5, 4-20, since Unit 1 was subsequently 4-5,4-20, subsequently licensed CLTP.
licensed to CL CLTP TP. CL applicable for TP is applicable for 6-2 all three units.
- 3. 1-2 Clarified that future licensing Clarified licensing of MELLLA+ is supported via via ((
].
].
AREVA NP Inc.
1,2, Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Extended Revision 0 Revision LOCA Break Spectrum Analysis Page Page iiii Contents Contents 1.0 1.0 Introduction Introduction ....................................................................................................................
.................................................... 1-1 1-1 2.0 Summary Sum mary of Results Results .......................................................................................................
....................................................................................................... 2-1 3.0 LOCA Description Description ..........................................................................................................
.......................................................................................................... 3-1 3.1 Accident Description Accident Description ...........................................................................................
........................................................................................... 3-1 3.2 Acceptance Acceptance Criteria ............................................................................................
Criteria ............................................................................................ 3-2 3-2 4.0 LOCA Analysis Analysis Description Description ...........................................................................................
...................................................................................... .4-1 4-1 4.1 Blowdown Analysis .............................................................................................
Blowdown ............................................................................................. 4-1 4.2 Refill / Reflood Analysis ............................ Refill! ......................................................................................
- ........................................................ .4-2 4-2 4.3 Heatup Analysis .................................................................................................
Heatup ................................................................................................. 4-2 4-2 4.4 Plant Parameters ................................................................................................ Parameters ................................................................................................ 4-3 4.5 ECCS Parameters Parameters ..............................................................................................
.............................................................................................. 4-3 4-3 5.0 Break Spectrum Analysis Description ............................................................................
Description ............................................................................ 5-1 5.1 Lim iting Single Failure Limiting Failure ........................................................................................
.................................................................................... 5-1 5.2 ...................................................................................
Recirculation Line Breaks ................................................................................... 5-1 5.3 Non-Recirculation Line Breaks ........................................................................... Non-Recirculation ........................................................................... 5-3 5-3 5.3.1 HPCI Line Breaks .................................................................................
................................................................................. 5-3 5-3 5.3.2 LPCS Line Breaks ................................................................................
Breaks ................................................................................ 5-4 5-4 5.3.3 LPCI Line Breaks .................................................................................
................................................................................. 5-4 5-4 5.3.4 Main SteamSteam Line Breaks ..................................................................
...................................................................... 5-4 5-4 5.3.5 Feedwater Line Breaks ........................................................................
Feedwater ........................................................................ 5-5 5-5 5.3.6 RCIC Line Breaks .................................................................................
................................................................................. 5-5 5-5 5.3.7 5 ..3.7 RW CU Line Breaks ..............................................................................
RWCU .............................................................................. 5-6 5-6 5.3.8 Instrum ent Line Breaks ........................................................................ Instrument ........................................................................ 5-6 5-6 6.0 Recirculation Line Break Recirculation Break LOCA Analyses ...................................................................... Analyses ...................................................................... 6-1 6.1 Lim iting Break Analysis Results Limiting ......................................................................... Results ......................................................................... 6-1 6.2 ........................................................................ Break Location Analysis Results ........................................................................ 6-2 6.3 Break Geometry and Size Analysis Results .......................................................
....................................................... 6-2 6.4 Limiting Lim iting Single-Failure Single-Failure Analysis Results .............................................................
............................................................. 6-2 6.5 Axial Power Shape Analysis Results ..................................................................
.................................................................. 6-2 6.6 State Point Analysis Analysis ...........................................................................................
........................................................................................... 6-2 6-2 7.0 Non-Recirculation Line LOCA Analysis Non-Recirculation ..........................................................................
Analysis .......................................................................... 7-1 7.1 Lim iting ECCS Line Break Results ..................................................................... Limiting ..................................................................... 7-1 8.0 Single-Loop Single-Loop Operation LOCA Analysis ..........................................................................
.......................................................................... 8-1 8.1 SLO Analysis Modeling Methodology Methodology .................................................................
............................................................ 8-1 8.2 SLO Analysis Results .........................................................................................
......................................................................................... 8-2 8-2 9.0 Long-Term ....................................................................................................
Long-Term Coolability .................................................................................................... 9-1 10.0 Conclusions .................................................................................................................. Conclusions .................................................................................................................. 10-1 11.0 References ................................................................................................................... References ................................................................................................................... 11-1 11-1 Appendix A Supplemental Supplemental Information ........................................................................... Information ............................................................................... A-1 AREVA NP Inc.
Browns Browns Ferry Units 1, 1,2,2, and 33 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Spectrum Analysis Page iii iii Tables Tables 44.1
.1 Initia l Conditions Initial .............................................................................................................
Co n d itio ns ............................................................................................................. 44-5
-5 4.2 Reactor System Parameters Param eters .........................................................................................
.......................................................................................... 4-6
.4-6 4.3 ATRIUM-10 Fuel Assembly Parameters ATRIUM-10 ........................................................................
Parameters ....................................................................... 4-7
.4-7 4.4 High-Pressure High-Pressure Coolant Injection Parameters Parameters .................................................................
................................................................ .4-8 4-8 4.5 Low-Pressure Low-Pressure Coolant Injection Injection Parameters .................................................................
.................................................................. 4-9
.4-9 4.6 Low-Pressure ........................................................................
Low-Pressure Core Spray Parameters ....................................................................... 4-10
.4-10 4.7 Depressurization System Parameters Automatic Depressurization ......................................................... .4-11 Parameters ........................................................ 4-11 4.8 Recirculation ................................................... .4-12 Recirculation Discharge Isolation Valve Parameters .................................................. 4-12 5.1 ECCS Single Failure ......... . ............... ....... .......... 5-7 5.2 Available ECCS for ECCS Line Break LOCAs ...............................................................
............................................................... 5-8 6.1 Results for Limiting TLO Recirculation Recirculation Line Break 0.5 ft ft22 Split Pump Discharge SF-BATT Mid-Peaked Mid-Peaked Axial 102% 102% EPU 105% 105% Flow .....................................
..................................... 6-3 6-3 6.2 Event Times for Limiting TLO Recirculation Recirculation Line Break 0.5 ft2 ft2 Split Pump Discharge SF-BATT Mid-Peaked Mid-Peaked Axial 102% 102% EPU 105% Flow .....................................
..................................... 6-4 6-4 6.3 Recirculation Line Break TLO Recirculation Spectrum Results for 102%
Break Spectrum 102% EPU 105% 105% Flow Flow S F -BAT T ......................................................................................................................... SF-BATT 66-5
-5 6.4 TLO Recirculation Recirculation Line Break Spectrum Spectrum Results for 102% 102% EPU 105% 105% Flow Flow S F-LO CA /DG E N ............................................................................................................
SF-LOCAIDGEN ............................................................................................................ 6-6 6-6 6.5 Recirculation Line Break Spectrum TLO Recirculation Spectrum Results for 102% 102% EPU 105% 105% Flow Flow S F-HP C I......................................................................................................................... SF-HPCI ......................................................................................................................... 66-7
-7 6.6 Recirculation Line Break Spectrum TLO Recirculation Spectrum Results for 102% 102% EPU 105% 105% Flow Flow S F-LP C I .........................................................................................................................
SF-LPCI .......................................................................................................................... -8 66-8 6.7 Recirculation Line Break Spectrum TLO Recirculation Spectrum Results for 102% 102% EPU EPU (( )) S F -BA TT ............................................................... SF-BATT ~ ........................................................ 6
........................................................................................................................ -9 6-9 6.8 Recirculation Line Break Spectrum TLO Recirculation Spectrum Results for 102% 102% CL CLTP TP 105%105% Flow Flow S F -BA TT ......................................................................................................................
SF-BATT ...................................................................................................................... 6 -10 6-10 6.9 Summary of TLO Recirculation Recirculation Line Break Results Highest Highest PCT Cases .................... 6-11
.................... 6-11 7.1 Event Times for Limiting ECCS Line Break 0.4 ft2 ft2 Double-Ended Double-Ended Guillotine SF-BATT Top-Peaked Top-Peaked Axial 102% ...................................... 7-2 102% EPU 105% Flow ...................................... 7-2 7.2 Non-Recirculation Line Break Non-Recirculation Spectrum Results for 102%
Break Spectrum 102% EPU ...................................
................................... 7-3 8.1 Results for Limiting SLO Recirculation Recirculation Line Break 0.6 ft2 ft2 Split Pump Discharge Discharge SF-BATT SF-BATT Mid-PeakedMid-Peaked Axial [ ] ................................
................................ 8-3 8-3 8.2 Event Times for Limiting SLO Recirculation Recirculation Line Break 0.6 ft2 ft2 Split Pump Discharge Discharge SF-BATT SF-BATT Mid-PeakedMid-Peaked Axial [ )) ................................
................................ 8-4 8-4 8.3 Recirculation Line Break Spectrum SLO Recirculation Spectrum Results ........................................................... 8-5
........................................................... 8-5 8.4 Single- and Two-Loop Two-Loop Operation PCT Summary ...........................................................
........................................................... 8-6 8-6 AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Extended Revision 0 Revision Spectrum Analysis LOCA Break Spectrum Page iv iv Figures Figures 4.1 Diagram for EXEM BWR-2000 ECCS Evaluation Flow Diagram Evaluation Model Model..................
............................ :...... .4-13 4-13 4.2 RELAX System BlowdownBlowdow n Model Model ................................................................................
............................................................................... .4-14 4-14 4.3 RELAX Hot Channel Blowdown Blowdown Model Top-Peaked Top-Peaked Axial Axial............................................
......................................... .4-15 4-15 4.4 RELAX Hot Channel Blowdown Blowdown Model Mid-Peaked Mid-Peaked Axial ...........................................
.......................................... .4-16 4-16 44.5
.5 ECCS S ECCS chem atic .........................................................................................................
Schematic ......................................................................................................... 4-17 4-17 4.6 Axial Power Distributions Distributions at 102% 102% EPU/105% .................................................... .4-18 EPU/105% Flow ................................................... 4-18 4.7 Axial Power Distributions Distributions at 102% 102% EPU/[ EPU/ [ ................................................. 4-19 I..................................................
]. 4-19 4.8 Axial Power Distribution Distribution at 102% 102% CL CLTP/105% .................................................... .4-20 TP/1 05% Flow ................................................... 4-20 6.1 Limiting TLO Recirculation Recirculation Line .................................. 6-12 Break Upper Plenum Pressure .................................. 6-12 6.2 Limiting TLO Recirculation Recirculation Line Break Total Break Flow Rate ....................................
.................................... 6-12 6-12 6.3 Limiting TLO Recirculation Line Break Core Inlet Flow Rate .......................................
....................................... 6-13 6-13 6.4 Recirculation Limiting TLO Recirculation Line Break Core Outlet Flow Rate ....................................
.................................... 6-13 6-13 6.5 Recirculation Limiting TLO Recirculation Line Break IntactIntact Loop Jet Pump Drive Flow Rate ........... ........... 6-14 6-14 6.6 Recirculation Limiting TLO Recirculation Line Break IntactIntact Loop Jet Pump Suction Flow Rate ........ 6-14
........ 6-14 6.7 Recirculation Limiting TLO Recirculation Line Break IntactIntact Loop Jet Pump Exit Flow Rate .............. .............. 6-15 6-15 6.8 Recirculation Limiting TLO Recirculation Line Break Broken Loop Jet Pump Drive Flow Rate ......... 6-15
......... 6-15 6.9 Recirculation Limiting TLO Recirculation Line Break Broken Loop Jet Pump Suction Suction Flow Rate ..... ..... 6-16 6-16 6.10 Limiting TLO Recirculation Recirculation Line Break Broken Loop Jet Pump Exit Flow Rate ........... 6-16
........... 6-16 6.11 Limiting TLO Recirculation Recirculation Line Break ADS Flow Rate ...............................................
............................................... 6-17 6-17 6.12 Limiting TLO Recirculation Recirculation Line .............................................
Break HPCI Flow Rate .............................................. 6-17 6-17 6.13 Limiting TLO Recirculation Recirculation Line Break LPCS Flow Rate .............................................
............................................. 6-18 6-18 6.14 Limiting TLO Recirculation Recirculation Line Break Intact ............................ 6-18 Intact Loop LPCI Flow Rate ............................ 6-18 6.15 Limiting TLO Recirculation Recirculation Line Break Broken Loop LPCI Flow Rate ......................... ......................... 6-19 6-19 6.16 Limiting TLO Recirculation Recirculation Line Break Upper Downcomer Mixture LeveL Upper Downcomer Level .................... 6-19
................... 6-19 6.17 Limiting TLO Recirculation Recirculation Line Break Lower Downcomer Downcomer Mixture LeveL Level ....................
................... 6-20 6.18 Limiting TLO Recirculation Recirculation Line Break Lower Downcomer Liquid Mass ...................... ...................... 6-20 6.19 Limiting TLO Recirculation Recirculation Line Break IntactIntact Loop DischargeDischarge Line Liquid Mass ......... ......... 6-21 6.20 Limiting TLO Recirculation Recirculation Line Break Upper ............................. 6-21 Upper Plenum Liquid Mass .............................
6.21 Limiting TLO Recirculation Recirculation Line Break Lower Plenum Liquid Mass ............................. ............................. 6-22 6-22 6.22 Limiting TLO Recirculation Recirculation Line Break Hot Channel Channel Inlet Flow Rate ...........................
........................... 6-22 6.23 Limiting TLO Recirculation Recirculation Line Break Hot Channel Channel Outlet Flow Rate ................................................ 6-236-23 6.24 Limiting TLO Recirculation Recirculation Line Break Hot Channel Channel Coolant Temperature Temperature at the the Lim iting Limiting ..................................................... ;......................................................... 66-23 No d e ...............................................................................................................
Node -23 6.25 Limiting Recirculation Line Break Hot Channel Quality at the Limiting Node ....... TLO Recirculation ....... 6-24 6-24 6.26 Limiting Recirculation Line Break Hot Channel TLO Recirculation Channel Heat Transfer Transfer Coef. at the the Lim iting Limiting No d e .............................................................................................................. Node ............................................................................................................... 6-24 6 -24 6.27 Limiting TLO Recirculation Recirculation Line Break Cladding Temperatures Temperatures ..................................
.................................. 6-25 6-25 AREVA NP Inc.
1,2, Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Spectrum Analysis Page v Figures (Continued) (Continued) 8.1 Limiting Recirculation SLO Recirculation ................................... 8-7 Line Break Upper Plenum Pressure ................................... 8-7 8.2 Limiting SLO Recirculation Recirculation Line Break Total Break Flow Rate ................. ...................................... 8-7 8-7 8.3 Limiting Recirculation SLO Recirculation Line Break Core Inlet Flow Rate .........................................
......................................... 8-8 8.4 Limiting Recirculation SLO Recirculation Line Break Core Outlet Flow Rate .................................. 8-8
...................................... ;... 8-8 8.5 Limiting Recirculation SLO Recirculation Line Break Intact Intact Loop Jet Pump Drive Flow Rate ............. ............. 8-9 8-9 8.6 Limiting SLO Recirculation Recirculation Line Break Intact Intact Loop Jet Pump Suction Flow Rate .......... .......... 8-9 8-9 8.7 Limiting Recirculation SLO Recirculation Line Break lritact Intact Loop Jet Pump Exit Flow Rate .............. .............. 8-10 8-10 8.8 Limiting SLO Recirculation Recirculation Line Break Broken Loop Jet Pump Drive Flow Rate ......... ......... 8-10 8-10 8.9 Limiting SLO Recirculation Recirculation Line Break Broken Loop Jet Pump Suction Flow Rate ..... ..... 8-11 8-11 8.10 Limiting Recirculation SLO Recirculation Line Break Broken Loop Jet Pump Exit Flow Rate ........... ........... 8-11 8-11 8.11 Limiting SLO Recirculation Recirculation Line Break ADS Flow Rate ...............................................
............................................... 8-12 8-12 8.12 Limiting SLO Recirculation Recirculation Line Break HPCI Flow Rate ..............................................
.............................................. 8-12 8-12 8.13 Limiting SLO Recirculation Recirculation Line Break LPCS Flow Rate .............................................
............................................. 8-13 8-13 8.14 Limiting SLO Recirculation Recirculation Line Break Intact Loop LPCI Flow Rate ............................ ............................ 8-13 8-13 8.15 Limiting SLO Recirculation Line Break Broken Broken Loop LPCI Flow Rate ......................... ......................... 8-14 8-14 8.16 Limiting SLO Recirculation Line Break Upper Downcomer Mixture Upper Downcomer Mixture Level ................... 8-14
................... 8-14 8.17 Limiting SLO Recirculation Line Break Lower Downcomer Mixture Mixture Level ................... 8-15
................... 8-15 8.18 Limiting SLO Recirculation Recirculation Line Break Lower Downcomer Liquid Mass ...................... 8-15
...................... 8-15 8.19 Limiting SLO Recirculation Recirculation Line Break Intact Loop Discharge Line Liquid Mass ......... 8-16
......... 8-16 8.20 Limiting SLO Recirculation Recirculation Line Break Upper Plenum Liquid Mass ............................. ............................. 8-16 8-16 8.21 Limiting Recirculation Line Break Lower Plenum Liquid Mass .............................
SLO Recirculation ............................. 8-17 8-17 8.22 Limiting Recirculation Line Break Hot Channel Inlet Flow Rate ........................... SLO Recirculation ........................... 8-17 8-1.7 8.23 Limiting Recirculation Line Break Hot Channel Outlet SLO Recirculation Flow Rate ........................
........................ 8-188-18 8.24 Limiting Recirculation Line Break Hot Channel Coolant Temperature SLO Recirculation Temperature at the the Lim iting Limiting No d e .......................................................................................
Node ....................... 88-18
............................................................................................................... -18 8.25 Limiting Recirculation Line Break Hot Channel Quality at the Limiting Node .......
SLO Recirculation 8-19
....... 8-19 8.26 Limiting Recirculation Line Break SLO Recirculation Break Hot Channel Heat Transfer Coef. at the the Lim iting Limiting No d e ...............................................................................................................
Node ............................................................................................................... 8-19 8-19 8.27 Limiting Recirculation Line Break SLO Recirculation Break Cladding Temperatures .................................. 8-20 Temperatures .................................. 8-20 This document contains contains a total total of 154 pages. pages. AREVA NP Inc. AREVA
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 Spectrum Analysis LOCA Break Spectrum Analysis Page vi Nomenclature Nomenclature ADS ADS automatic automatic depressurization depressurization system ADSVOOS ADSVOOS ADS valve out of service ANS ANS American American Nuclear Society BOL beginning of life beginnIng life BWR BWR boiling water water reactor CFR Code of Federal Regulations Regulations CHF CHF critical heat heat flux flux CLTP CLTP current licensed thermal thermal power (3458 MWt) MWt) CMWR CMWR core average metal-water reaction average metal-water DEG DEG double-ended guillotine double-ended guillotine DG DG generator diesel generator ECCS ECCS emergency core cooling system emergency EOB end of blowdown EPU extended extended power uprate uprate FFWTR FFWTR final feedwater temperature reduction feedwater temperature reduction FHOOS FHOOS feedwater heaters out of service feedwater heaters service FSAR Final Safety Safety Analysis Report HPCI high-pressure coolant injection high-pressure LOCA loss-of-coolant accident loss-of-coolant accident LPCI low-pressure coolant injection low-pressure injection LPCS LPCS low-pressure low-pressure core spray MAPLHGR MAPLHGR maximum average planar maximum average planar linear heat generation generation rate MCPR MCPR minimum critical ratio critical power ratio MELLLA MELLLA maximum extended maximum extended load line limit analysis analysis MELLLA+ MELLLA+ MELLLA-plus (EPU extension MELLLA-plus extension of MELLLA) MSIV MSIV main steam isolation valve valve MWR MWR metal-water metal-water reaction NRC NRC Nuclear Regulatory Commission, Nuclear Regulatory Commission, U.S. OLTP OLTP original licensed thermal thermal power PCT peak cladding temperature temperature RCIC RCIC reactor core isolation cooling cooling RDIV RDIV recirculation recirculation discharge discharge isolation valvevalve RWCU reactor water cleanup cleanup AREVA AREVA NP Inc.
Browns Ferry Units Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Uprate Revision 0 Revision Spectrum Analysis LOCA Break Spectrum Page vii Nomenclature (Continued) Nomenclature (Continued) SF-ADS single failure of an ADS valve valve SF-BATT single failure of battery (DC) power SF-DGEN SF-DGEN single failure of a diesel generator generator SF-HPCI SF-HPCI single failure of the HPCI system system SF-LOCA single failure of opposite unit false LOCA signal SF-LPCI SF-LPCI single failure of a LPCI valve valve SLO single-loop operation operation TLO operation. two-loop operation. AREVA NP Inc.
Browns Browns Ferry Units 1, 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Extended Power Uprate Revision Revision 0 LOCA Break Spectrum Spectrum Analysis Page 1-1 1-1 1.0 1.0 Introduction Introduction The results of a loss-of-coolant loss-of-coolant accident accident (LOCA) break spectrum analysis for Browns Browns Ferry Ferry Units 1, 2, and 3 are documented documented in this report. The purpose purpose of the break spectrum analysis is to identify parameters that result in the highest calculated peak cladding identify the parameters temperature (PCT) cladding temperature postulated LOCA. The LOCA parameters during a postulated parameters addressed addressed in this report include include the following:
- Break location Break location
- Break Break type (double-ended guillotine guillotine (DEG)
(OEG) or split)
- size Break size
- 0 Limiting emergency emergency core cooling system (ECCS) single single failure 0* Axial power power shape (top- or mid-peaked) mid-peaked)
The analyses documented in this report were performed with LOCA Evaluation Models analyses documented Models developed by AREVA developed AREVA NP* and approvedapproved for reactor licensing licensing analyses by the Nuclear Nuclear Regulatory Commission, U.S. (NRC). The models and computer computer codes used by AREVA for for LOCA analyses analyses are collectively referred referred to as the EXEM BWR-2000 BWR-2000 Evaluation Evaluation Model. The Model. The EXEM BWR-2000 Evaluation Model and NRC documented in Reference NRC approval are documented Reference 1. A summary description methodology is provided description of the LOCA analysis methodology provided in Section The Section 4.0. The calculations calculations described in this report were performedperformed in conformance conformance with 10 CFR 50 Appendix Appendix K K requirements requirements and satisfy the event acceptance acceptance criteria identified identified in 10 CFR 50.46. The break spectrum analyses documented in this report were performed for a core composed analyses documented entirely ATRIUMTM-10t fuel at beginning-of-life entirely of ATRIUMTM-10t beginning-of-life (BOL) conditions. Calculations assumedassumed an initial core power power of 102%102% of 3952 MWt as per NRC requirements. 3952 MWt MWt corresponds to 120% of the original licensed 120% licensed thermal power (OL (OLTP) TP) and is referred referred to as the extended extended power power uprate (EPU). In addition to the EPU power level, an additional analysis was made for the the limiting single failure and break size for 102% of 3458 MWt. 3458 3458 MWt corresponds to the the current licensed thermal power (CLTP), power (CL TP), which is 105% 105% OL OLTP. CLTP TP. CL presented to TP analysis is presented to demonstrate demonstrate that the limiting EPU case bounding for CL case is bounding CLTP TP operation. Based on similar similar limiting break sizes sizes of EPU 105% 105% and [ ] and SLO, the limiting limiting break CLTP CLTP analysis analysis was chosen as 0.5 ff. ft2 . The limiting assembly assembly in the core was assumed assumed to be at a maximum maximum axial planar heat generation generation rate (MAPLHGR) (MAPLHGR) limit of 12.5 kW/ft. The analyses assumed assumed a generic generic AREVA NP Inc. is an AREVA and Siemens company. AREVA NP Inc. is an AREVA and Siemens company. tt ATRIUM is a trademark of AREVA NP. ATRIUM is a trademark of AREVA NP. AREVA NP Inc.
Browns Ferry Units 1,1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Revision 0 LOCA Break Spectrum Spectrum Analysis Page 1-2 'ATRIUM-10 neutronic design. Other initial conditions used in the analyses ATRIUM-10 neutronic analyses are described described in in Section 4.0. This report identifies identifies the limiting LOCA break characteristics (location, break characteristics (location, type, size, single failure, and axial power shape) that will be used in future analyses to determine determine the MAPLHGR MAPLHGR limitlimit versus exposure for ATRIUM-10 ATRIUM-10 fuel contained contained in Browns Ferry Ferry Units 1, 2, and 3. Even Even though the limiting break break will not change exposure or ATRIUM-10 change with exposure nuclear fuel design, the value of ATRIUM-10 nuclear of PCT calculated for any given set of break characteristics characteristics is dependent dependent on exposure exposure and local power peaking. Therefore, heatupheatup analyses are performed performed to determine determine the PCT versus versus exposure for each ATRIUM-10 nuclear design in the core. The heatup analyses ATRIUM-10 nuclear analyses are performed performed boundary conditions determined each cycle using the limiting boundary determined in the break break spectrum analysis. The maximum PCT versus versus exposure exposure from the heatup analyses documented in the analyses are documented the MAPLHGR report. MAPLHGR All analyses analyses were performed performed assuming automatic automatic depressurization depressurization system (ADS) valves in- in-out-of-service (ADSVOOS) operation. (( service. This report does not support ADS valve out-of-service maximum
] Future EPU maximum extended load line limit analysis extended (MELLLA+) licensing analysis (MELLLA+) operation is supported licensing and operation supported via analyses analyses
(( )) The operating domain of the power/flow power/flow map of Reference 6 (which MELLLA+ and bounds MELLLA) is applicable for the ATRIUM-10. includes MELLLA+ ATRIUM-10. This report also presents results for single-loop operation operation (SLO). AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Break Spectrum Analysis Analysis Page 2-1 2.0 Summary of Results Summary Results Based on analyses presented in this report, the limiting break characteristics analyses presented identified characteristics are identified below. Limiting LOCA Limiting LOCA Break Characteristics Characteristics Location recirculation pipe recirculation discharge pipe 2 Type /I size split / 0.5 split I 0.5 fe ft Single failure Single power battery (DC) power power shape Axial power mid-peaked mid-peaked Reactor operation [ ]I Initial state 102% EPU 102% EPU /I 105% rated flow flow A more detailed discussion discussion of results is provided Sections 6.0 - 8.0. provided in Sections [
] The break characteristics identified in this report can break characteristics be used in subsequent fuel type typ~ specific specific LOCA hot channel and heatup analyses to determine determine appropriate for the ATRIUM-1 MAPLHGR limit appropriate the MAPLHGR ATRIUM-10 0 fuel type.
analyses support operation with an ATRIUM-10 The SLO LOCA analyses MAPLHGR multiplier of 0.85 ATRIUM-10 MAPLHGR 0.85 applied to the normal two-loop operation MAPLHGR MAPLHGR limit. analyses support operation with six ADS valves. No ADS valves are assumed out-of-service. All analyses [ A
] All analyses were performed assuming nominal feedwater temperature. [
] All analyses were performed assuming nominal feedwater temperature. [
AREVA NP Inc.
Units 1, 2, and Browns Ferry Units and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Extended Power Uprate Uprate Revision Revision 0 Spectrum Analysis LOCA Break Spectrum Analysis Page Page 2-2 2-2
] The conclusions conclusions ofof this report are are applicable applicable for for operation with six ADS, [
operation ], MELLLA+, MELLLA+, FHOOS, FFWTR, andand SLO. While the the fuel rod temperatures temperatures in the limiting plane plane of the the hot hot channel channel during aa LOCA are exposure, the factors that determine dependent on exposure, dependent limiting break determine the limiting break characteristics characteristics are primarily associated associated with the reactor system and are not dependentdependent on fuel-exposure fuel-exposure characteristics. characteristics. Fuel parameters that Fuel parameters that are dependent dependent on exposure exposure (e.g., stored energy, local peaking) have an insignificant insignificant effect effect on the reactor reactor system response during aa LOCA. The The limiting break characteristics determined using BOL fuel conditions are applicable characteristics determined applicable for exposed exposure effects fuel. Fuel exposure effects are addressed addressed in heatup analyses analyses performed performed to determine determine or verify MAPLHGR MAPLHGR limits versus exposure exposure for for each ATRIUM-10 ATRIUM-10 fuel design. design. The break break spectrum spectrum analysis was performed performed using using the NRC-approved NRC-approved AREVAAREVA EXEM BWR-2000 LOCA methodology. All SER restrictions restrictions and ranges of applicability applicability for the EXEM BWR-2000 methodology methodology were reviewed prior to final documentation documentation of the LOCA analysis analysis to ensure compliance with NRC requirements methodology limitations. requirements and methodology Inc. AREVA NP Inc.
Browns Ferry Units 1,2, 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Spectrum Analysis Page 3-1 3.0 LOCA Description LOeA Description 3.1 Accident Description Description The LOCA is described described in the Code of Federal Regulations 10 CFR 50.46 as a hypothetical accident that results in a loss of reactor coolant from breaks accident breaks in reactor coolant pressure boundary boundary piping up to and including including a break equivalent equivalent in size to a double-ended double-ended rupture rupture of thethe largest largest pipe in the reactor coolant coolant system. There is not a specifically identified identified cause that results results in the pipe break. However, for the purpose of identifying identifying a design basis accident, the pipe pipe break is postulated postulated to occur inside the primary containment containment before before the first isolation valve. For a BWR, a LOCA may occur over a wide spectrum spectrum of break locations locations and sizes. Responses Responses to the break break vary significantly significantly over the break spectrum. The largest possible break break is a double-ended rupture of a recirculation recirculation pipe; however, this is not necessarily necessarily the most most severe challenge challenge to the emergency emergency core cooling system (ECCS). A double-ended double-ended rupture rupture of a main steam line line causes the most rapid primary depressurization, but because of other phenomena, primary system depressurization, steam line breaks are seldom limiting limiting with respect respect to the criteria of 10 10 CFR 50.46. Special considerations are required when the break is postulated analysis considerations postulated to occur in a pipe that is used as the injection path for an ECCS (e.g. core spray line). Although these breaks are relatively relatively small, their existence existence disables disables the function of an ECCS. In addition to break location dependence, different different break break sizes in the same pipe produce quite different event responses, and the largest break area is not necessarily necessarily the most severe challenge to the event acceptance acceptance criteria. Because of these complexities, complexities, an analysis covering the full range of breakbreak sizes and locations locations is required. Regardless of the initiating break characteristics, Regardless characteristics, the event response is conveniently conveniently separated into three phases: the blowdown blowdown phase, the refill phase, and the reflood phase. The relative relative duration of each phase is strongly dependent upon the break size and location. The last two duration phases are often combined and will be discussed together together in this report. During During the blowdown blowdown phase of a LOCA, there is a net loss of coolant inventory,inventory, an increase increase in fuel cladding temperature due to core flow degradation, degradation, and for the larger larger breaks, the core becomes becomes fully or partially uncovered. There is a rapid decrease pressure during the blowdown decrease in pressure blowdown phase. During the early phase of the depressurization, depressurization, the exiting coolant provides provides core cooling. Low-pressure Low-pressure core spray (LPCS) also provides some heat heat removal. The blowdown blowdown phase is defined to end when LPCS reaches reaches rated flow. AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 Revision LOCA Break Spectrum Spectrum Analysis 3-2 Page 3-2 increase of coolant functioning and there is a net increase In the refill phase of a LOCA, the ECCS is functioning coolant inventory. During this phase the core sprays provide core cooling and, along with low-pressure low-pressure high-pressure coolant and high-pressure coolant Injection lower portion of (LPCI and HPCI), supply liquid to refill the lower injection (LPCI the reactor vessel. In general, the core heat transfer to the coolant is less than the fuel decay heat rate and the fuel cladding temperature continues to increase during the refill phase. temperature continues In the reflood phase, the coolant inventory increased to the point where the mixture inventory has increased mixture level reenters the core region. During the core reflood reenters reflood phase, cooling is provided above the mixturemixture entrained reflood liquid and below level by entrained below the mixture mixture level by pool boiling. Sufficient coolant eventually eventually reaches'the reaches the core hot nodenode and the fuel cladding temperature temperature decreases. 3.2 Criteria Acceptance Criteria place constraints on fuel design, local potentially limiting event that may place A LOCA is a potentially power local power acceptable core power level. During aa LOCA, the normal transfer peaking, and in some cases, acceptable of heat from the fuel to the coolant is disrupted. As the liquid inventory in the reactor decreases, the decay heatheat and stored energy of the fuel cause a heatup undercooled fuel assembly. heatup of the undercooled In order to limit the amount of heat that can contribute heatup of the fuel assembly contribute to the heatup during assembly during MAPLHGR is applied to each operating limit on the MAPLHGR a LOCA, an operating assembly in the core. each fuel assembly The Code of Federal Regulations prescribes specific Regulations prescribes specific acceptance criteria (10 CFR 50.46) for aa acceptance criteria LOCA event as well as specific requirements and acceptable specific requirements acceptable features for Evaluation ModelsModels conformance of the EXEM Appendix K). The conformance (10 CFR 50 Appendix EXEM BWR-2000 BWR-2000 LOCA Evaluation Models Models to Appendix K is described Reference 1. The ECCS must be designed described in Reference designed such that the plant response to a LOCA meets the following acceptance specified in 10 CFR 50.46: acceptance criteria specified
** calculated maximum fuel element The calculated element cladding 2200°F.
temperature shall not exceed 2200°F. cladding temperature
** The calculated The local oxidation calculated local oxidation of of the cladding shall the cladding shall nowhere exceed 0.17 nowhere exceed times the 0.17 times the local local cladding thickness.
- The calculated calculated total amount generated from the chemical amount of hydrogen generated chemical reaction reaction of the the cladding with water or steam shall not exceed 0.01 times the hypothetical cladding hypothetical amount that generated if all of the metal would be generated cladding cylinders surrounding metal in the cladding surrounding the fuel, except the cladding cladding surrounding surrounding the plenum volume, were to react.
- Calculated Calculated changes geometry shall be such that the core remains amenable changes in core geometry amenable to cooling.
- After any calculated successful operation of the ECCS, the calculated successful operation temperature calculated core temperature maintained for the extended period of time required by the long-lived shall be maintained long-lived radioactivity remaining in the core.
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1, 2, and 3 Browns Ferry Units 1, EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Revision 0 LOCA Break Spectrum Spectrum Analysis Page 3-3 3-3 These criteria are commonly referred referred to as the peak cladding cladding temperature temperature (PCT) criterion, the the local local oxidation criterion, the hydrogen generation generation criterion, criterion, the coolable geometry criterion, and MAPLHGR limit is established the long-term cooling criterion. A MAPLHGR established for the ATRIUM-10 ATRIUM-10 fuel type to ensure that these criteria are met. LOCA PCT results are provided provided in Sections 6.0 - 8.0 to determine the limiting LOCA event. LOCA analysis results demonstrating determine demonstrating that the PCT, local oxidation, and hydrogen oxidation, hydrogen generation criteria are met are provided provided in the follow-on MAPLHGR MAPLHGR report and cycle-specific cycle-specific heatup heatup analyses. analyses. Cycle-specific Cycle-specific heatup analyses performed to analyses are performed demonstrate demonstrate that the MAPLHGR MAPLHGR limits versus exposure exposure for the ATRIUM-10 ATRIUM-10 fuel remains remains applicable cycle-specific nuclear designs. Compliance applicable for cycle-specific Compliance with these three criteria ensures that a coolable coolable geometry geometry is maintained. maintained. Long-term coolability coolability criterion criterion is discussed discussed in Section Section 9.0. AREVA NP Inc.
1, 2, and 3 Browns Ferry Units 1, EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Revision 0 Spectrum Analysis LOCA Break Spectrum Page 4-1 4.0 LOCA Analysis Description The Evaluation Evaluation Model used for the break spectrum analysis analysis is the EXEM BWR-2000 LOCA analysis methodology analysis methodology described in Reference Reference 1. The EXEM EXEM BWR-2000 BWR-2000 methodology employs methodology employs three major computer codes to evaluate evaluate the system and fuel response phases of a response during all phases LOCA. These are the RELAX, HUXY, and RODEX2 computer computer codes. RELAX RELAX is used to calculate calculate the system and hot channel response response during during the blowdown, blowdown, refill and reflood phases phases of the LOCA. The HUXY HUXY code code is used to perform heatup calculations for the entire LOCA, and calculates calculates the PCT and local clad oxidation at the axial plane of interest. RODEX2 is used to determine determine fuel parameters parameters (such as stored stored energy) for input to the other LOCA codes. The code code interfaces for the LOCA methodology are illustrated in Figure 4.1. interfaces 4.1. A complete complete analysis for a given break size starts with the specification specification of fuel parameters using parameters using RODEX2 (Reference RODEX2 (Reference 4). RODEX2 RODEX2 is used to determine determine the initial stored energy for both the the blowdown analysis (RELAX blowdown (RELAX system and hot channel) and the heatup analysis (HUXY). (HUXY). This is accomplished by ensuring that the initial stored energy accomplished energy in RELAX and HUXY HUXY is the same or higher than that calculated calculated by RODEX2 for the power, exposure, and fuel design being design being considered. 4.1 Blowdown Analysis The RELAX RELAX code (Reference (Reference 1) is used to calculate the system thermal-hydraulic thermal-hydraulic response response during the blowdown blowdown phase of the LOCA. For the system blowdown analysis, the core is system blowdown represented average core channel. The reactor core is modeled represented by an average modeled with heat generation generation rates determined from reactor kinetics equations with reactivity rates determined reactivity feedback and with decay heating as required by Appendix K of 10 CFR 50. The reactor vessel nodalization nodalization for the system blowdown analysis is shown in Figure 4.2. This nodalization nodalization is consistent consistent with that used in the the topical report submitted to the NRC (Reference (Reference 1). The RELAX analysis analysis is performed performed from the time of the break initiation through the end of blowdown (EOB). The system blowdown blowdown calculation calculation provides the upper and lower plenum plenum transient boundary conditions for the hot channel analysis. Following the system blowdown calculation, another blowdown calculation, another RELAX analysis analysis is performed performed to analyze analyze the maximum power assembly (hot channel) of the core. The RELAX hot channel calculation is used to calculate calculate hot channel channel fuel, cladding, and coolant temperatures temperatures during the blowdown AREVA NP Inc.
Browns Ferry Units 1, 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Revision 0 Revision LOCA Break Spectrum Spectrum Analysis Analysis Page 4-2 phase of the LOGA. LOCA. The RELAX hot channel nodalization is shown in Figure 4.3 for a top-peaked power power shape, and in Figure Figure 4.4 for a mid-peaked mid-peaked axial power shape. The hot channel performed using the system blowdown results to supply the core power and the analysis is performed the system boundary boundary conditions at the core inlet inlet and exit. The results from the RELAX hot channel calculation used as input to the HUXY calculation HUXY heatup analysis are heat transfer coefficients fluid coefficients and fluid conditions in the hot channel. 4.2 Refill / Reflood Analysis The RELAX code is used to compute compute the system and hot channel channel hydraulic response during the the refill/reflood phase of the LOGA. LOCA. The RELAX system and RELAX RELAX hot channel channel analyses continue continue beyond the end of blowdown to analyze system and hot channel responses during the refill and reflood phases. The refill phase is the period period when the lower plenum is filling due ECCS due to EGGS injection. The reflood phase is when some portions of the core and hot assembly being assembly are being cooled ECCS water entering from the lower plenum. The purpose of the RELAX cooled with EGGS calculations beyond blowdown is to determine beyond blowdown determine the the time when the liquid flow via upward entrainment from the bottombottom of the core becomes high enough at the hot node in the hot assembly to end the temperature temperature increase of the fuel rod cladding. This event time is called the the time of hot node reflood. ((
] The time when the core bypass mixture level rises to the elevation of the hot node in the hot assembly assembly is also determined.
RELAX provides a prediction of fluid inventory during the EGGS ECCS injection period. period. Allowing Allowing for for countercurrent flow through the core and bypass, RELAX determines countercurrentflow determines the refill rate of the lower plenum due to EGGS ECCS water and the subsequent subsequent reflood times for the core, hot assembly, and the core bypass. The RELAX calculations provide provide HUXY HUXY with the time of hot node reflood and the time when the liquid has risen in the bypass to the height of the axial plane of interest (time (time of bypass reflood). 4.3 Heatup Analysis Heatup The HU(XY HUXY code (Reference (Reference 2) is used to perform heatup calculations calculations for the entire LOGA LOCA transient and provides PCT PGT and local clad oxidation oxidation at the axial plane of interest. The heat heat generated by metal-water metal-water reaction (MWR) (MWR) is included in the HUXY HUXY analysis. HUXY is used to calculate the thermal thermal response of each fuel rod in one axial plane plane of the hot channel channel assembly. AREVA AREVA NP Inc.
Browns Ferry Units 1,1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Revision 0 LOCA Break Spectrum Spectrum Analysis Page 4-3 4-3 These calculations consider consider thermal-mechanical thermal-mechanical interactions interactions within the fuel rod. The clad clad swelling and rupture models from NUREG-0630 NUREG-0630 have been incorporated incorporated into HUXY (Reference (Reference 3). The HUXY code complies complies with the 10 GFRCFR 50 Appendix K K criteria for LOGA LOCA Evaluation Models. HUXY uses the end of blowdown blowdown time and the times of core bypass reflood and core reflood at the axial plane of interest from the RELAX analysis. ((
))
Throughout Throughout the calculations, calculations, decay power power is determined determined based on the ANS 1971 1971 decay heat Reference 1. [ curve plus 20% as described in Reference
)) used in the HUXY HUXY analysis. The principal heatup principal results of a HUXY heatup analysis are the PCT PGT and the percent percent local oxidation of the fuel cladding, cladding, often called thethe
%MWR. %MWR. 4.4 PlantParameters Plant Parameters The LOCA LOGA break spectrum analysis is performedperformed using the plant parameters parameters presented presented inin Reference Reference 6. Table 4.1 provides provides a summary of reactor initial initial conditions used in the break spectrum analysis. Table 4.2 lists selected selected reactor reactor system parameters. parameters. The break spectrum analysis performed for a full core of ATRIUM-10 analysis is performed ATRIUM-10 fuel. Some of the key ATRIUM-10 fuel parameters ATRIUM-10 parameters used in the break spectrum spectrum analysis are summarized summarized in Table Table 4.3. 4.5 ECCS Parameters ECCS Parameters The EGGS ECCS configuration configuration is shown in Figure 4.5. Tables 4.4 - 4.8 provide the important EGGS ECCS characteristics characteristics assumed in the analysis. The ECCS EGGS is modeled as fill junctions junctions connected to the the appropriate appropriate reactor locations: LPGS LPCS injects into the upper plenum, HPGI HPCI injects into the upper upper downcomer, and LPCI LPGI injects into the recirculation recirculation lines. The flow through each EGGS ECCS valve is determined determined based on system pressure pressure and valve position. Flow versus versus pressure pressure for a fully open valve is obtained by linearly interpolating interpolating the pump pump capacity capacity data provided provided in Tables 4.4 - 4.6. No credit for EGGS ECCS flow is assumed assumed until EGGS ECCS pumps reach rated speed. AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Spectrum Analysis Analysis Page 4-4 4-4 modeled as a junction connecting The ADS valves are modeled connecting the reactor steam line to the suppression calculated based on pressure pool. The flow through the ADS valves is calculated flow pressure and valve flow characteristics. The valve flow characteristics characteristics. determined such that the calculated characteristics are determined calculated flow is reference pressure shown capacity at the reference equal to the rated capacity Table 4.7. All six ADS valves are shown in Table are analyses do not support ADSVOOS assumed operable. The analyses operation. ADSVOOS operation. In the AREVA LOCA analysis model, ECCS initiation is assumed assumed to occur when the water water level applicable level setpoint. No credit is assumed for the start of HPCI, drops to the applicable HPCI, LPCS, or LPCI drywell pressure. (( due to high drywell
))
The recirculation discharge isolation valve (RDIV) parameters are shown in Table 4.8. The recirculation discharge isolation valve (RDIV) parameters are shown in Table 4.8. AREVA NP Inc.
Browns Ferry Units 1, 2, andand 3 EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Extended Revision 0 Analysis LOCA Break Spectrum Analysis Page 4-5 4-5 Table 4.1 Initial Initial Conditions* Reactor power power (% of rated) 102 EPU 102 102 EPU CLTP 102 CLTP Total core flow (% of rated) 105 105 [ 1 105 105 Reactor power (MWt) power (MWt) 4031 4031 3527 Total core flow (Mlb/hr) 107.6 107.6 [ ] 1 107.6 107.6 ((] ] Steam flow rate (Mlb/hr) (Mlb/hr) 16.82 16.82 16.82 16.82 14.47 14.47 Steam dome pressure pressure (psia) 1054 1054 1054 1054 1054 Core inlet enthalpy (Btu/lb) 522.9 [ ] 1 525.0 ATRIUM-10 assembly ATRIUM-10 hot assembly MAPLHGR (kW/ft) MAPLHGR 12.5 12.5 12.5 12.5 12.5 ((
]
temperature (OF):!: ECCS fluid temperature (°F)* 125 125 125 125 Axial power power shape Fig. 4.6 Fig. 4.7 Fig. 4.8 4.8
- calculated heat balance The AREVA calculated balance is adjusted to match the 100%
100% power/100% power/1 00% flow values values given in the plant parameters document document (Reference rebalanced based on AREVA heat (Reference 6). The model is then rebalanced balance balance calculations establish these calculations to establish these LOCA initial conditions at 102% 102% of rated thermal power. t t ((I ]
- t: temperature is determined Coolant temperature temperature versus time data.
determined from suppression pool temperature AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Uprate Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 4-6 4-6 Table 4.2 Reactor Reactor System Parameters Parameters Parameter Parameter Value Value Vessel 10 ID (in) (in) 251 Number of fuel assemblies 764 764 Recirculation suction pipe Recirculation pipe (ft2 ) area (ft2) 3.507 3.507 1.0 1.0 DEG OEG suction break (ft2) area (W) 7.013 7.013 Recirculation discharge Recirculation pipe discharge pipe (ft2) area (W) 3.507 3.507 1.0 DEG discharge break OEG discharge (ft2) area (W) 7.013 7.013 AREVA NP Inc.
Browns Browns Ferry Units Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Revision Revision 0 LOCA Break Spectrum Spectrum Analysis Analysis Page 4-7 Page 4-7 Table 4.3 ATRIUM-10 ATRIUM-10 Fuel Parameters Assembly Parameters Parameter Parameter Value Value Fuel rod array 1Ox10 10x10 Number of fuel rods per Number 83 83 (full-length rods) (full-length rods) assembly 8 (part-length (part-length rods) Non-fuel rod type Non-fuel replaces Water channel replaces 9 fuel rods 9 rods Fuel rod OD (in) 00 (in) 0.3957 (in) Active fuel length (in) 149.45 149.45 (full-length rods) (including blankets) 90 (part-length (part-length rods) Water channel channel outside width (in) (in) 1.378 1.378 Fuel channel channel thickness (in) (in) 0.075 (minimum wall) 0.100 (corner) Fuel channel channel internal (in) internal width (in) 5.278 AREVA NP Inc.
Browns Ferry Units Browns Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Power Uprate Uprate Revision Revision 0 LOCA Break Break Spectrum Analysis Analysis Page 4-8 Table 4.4 High-Pressure High-Pressure Coolant Coolant Parameters Injection Parameters Parameter Parameter Value Value Coolant temperature temperature CF)* (OF)* 125 125 InitiatingSignals Initiating and Setpoints Setpoints level t Water levelt L2 (448 in) High drywell drywell pressure (psig) 2.6 Time Time Delays Delays Time for HPCI pump to reach rated speed and injection injection valve valve wide open (sec) 50 50 Delivered Delivered Flow Rate Versus Pressure Pressure Vessel to Flow Flow Drywell AP
~P Rate Rate (psid) (gpm) 0o o0 150 4500 4500 1120 4500
- Coolant temperature is determined from suppression pool temperature versus time data.
- Coolant temperature is determined from suppression pool temperature versus time data.
tt Relative to Relative to vessel zero. vessel zero. AREVA NP Inc Inc...
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Extended Power Uprate Uprate Revision Revision 0 LOCA Break Spectrum Spectrum Analysis Analysis Page 4-9 Page 4-9 Table 4.5 Low-Pressure Low-Pressure CoolantCoolant Injection Parameters Injection Parameters Parameter Parameter Value Value permissive for Reactor pressure permissive Reactor opening valves (psia) 350 Coolant temperature temperature (OF)*CF)* 125 125 Initiating Initiating Signals and and Setpoints leveltt Water level Li L 1 (372.5 in) in) High drywell pressure pressure (psig) 2.6 2.6 Time Delays Time for LPCI pumps to reach rated speed (max) (sec):!: (sec)* 44 LPCI injection valve strokestroke (sec) time (sec) 40 DeliveredFlow Rate Delivered Pressure Versus Pressure Flow Rate Flow Rate Vessel Vessel (gpm) to (gpm) to Drywell ~PAP 2 Pumps Pumps 4 Pumps (psid) Into Into Into 1 Loop 2 Loops Loops 0 17,240 17,240 34,480 34,480 20 16,540 16,540 33,080§ 319.5 0 0
- Coolant temperature temperature is determined suppression pool temperature determined from suppression temperature versus versus time data.
tt Relative to vessel zero. Relative to vessel zero.
- I:* Includes 13-second Includes generator start. 2-second 13-second delay for diesel generator 2-second signal processing processing delay for water level trip Li L 1 is assumed in parallel generator delay.
parallel with diesel generator
§ § Conservative value Conservative value relative to specified specified value value in Reference limitations Reference 6 (33,240 gpm). Modeling limitations require the more value of either more conservative value either the specified 4 pumps into 2 loops flow or twice the the specified 2 pumps into 1 loop flow be used.
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Browns Ferry Units 1, 2, and 3 Browns EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Uprate Revision Revision 0 LOCA Break Spectrum Analysis Spectrum Analysis Page 4-10 4-10 Table 4.6 Low-Pressure Low-Pressure Core Parameters Spray Parameters Parameter Value Value permissive for Reactor pressure permissive opening valves (psia) 350 350 Coolant temperature temperature (OF)* CF)* 125 125 Initiating Signals Initiating Signals and Setpoints and Setpoints leveltt Water level Li L 1 (372.5 in)in) High drywell pressure pressure (psig) 2.6 2.6 Time Delays Time for LPCS pumps to reach ADS permissive permissive (max) (seer!: (sec)t 40 40 Time for LPCS pumps to reach rated speed (max) (sec):!: (sec)t 43 43 LPCS injection injection valve stroke stroke time (sec) (sec) 33 33 Delivered Flow Rate Delivered Versus Pressure Pressure Flow Rate Vessel Vessel to (gpm) (gpm) Drywell AP ilP 2 Pumps 4 Pumps Pumps (psid) Into Into 1 Sparger Sparger 2 Spargers 0o 6,935 13,870 13,870 105 5,435 10,870 10,870 289 o 0 o 0
- Coolant temperature temperature is determined determined from suppression suppression pool temperature versus time data.
temperature versus tt Relative to Relative to vessel zero. vessel zero.
- j:
Includes 13-second delay for diesel generator 13-second generator start. 2-second 2-second signal processing processing delay for water level trip Li L 1 is assumed in parallel assumed parallel with diesel generator delay. generator delay .. AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Revision 0 Analysis LOCA Break Spectrum Analysis Page 4-11 4-11 Automatic Depressurization Table 4.7 Automatic Depressurization System Parameters Parameters Parameter Parameter Value Value Number Number of valves installed 6 Number of valves available 6 Minimum flow capacity capacity of available valves valves (Mlbm/hr at psig) 4.8 at 1125 1125 InitiatingSignals Initiating Signals and Setpoints Setpoints Water level* LLi1 (372.5 in) in) LPCS ready permissive permissivett LLi1 + 40 sec (max) Time Time Delays Delay time (from ADS timer timer permissive to time valves are open) (sec) 120 120
- Relative to vessel zero.
t ADS timer initiation occurs occurs after level trip LLi1 is met and LPCS pumps reach the ADS ready conservatively not taken for the RHR pump ready permissive permissive (see Table 4.6). Credit is conservatively permissive that would occur 8 seconds earlier. AREVA NP Inc.
Units 1, 2, and 3 Browns Ferry Units Browns EMF-2950(NP) EMF-2950(NP) Extended Power Extended Uprate Power Uprate Revision Revision 0 Spectrum Analysis LOCA Break Spectrum Analysis Page 4-12 4-12 Recirculation Discharge Table 4.8 Recirculation Discharge Isolation Parameters Isolation Valve Parameters Parameter Parameter Value Value Reactor Reactor pressure permissive for closing valves --
-, analytical (psia) 215 215 stroke time after pressure RDIV stroke permissive (sec) 36 36 AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 Revision LOCA Break Spectrum Analysis Spectrum Analysis Page 4-13 4-13 I Fuel Data 11----------1:~ 1"iI~1----------l1 Plant Data I Neutronic Data Neutronic Data
..,. L...r ___ Core ~P,_ _
~RPF,APF System SS CoreT/H (CASMO-4, (CASM0-4, Analysis (XCOBRA)
MICROBURN-B2) MICROBURN-B2) (RELAX) Fuel Parameters I - - Fuel Stored .... (RODEX2) Energy -----,.. I
'---- Plenum -
Boundary Con:ions
,Ir ,
Hot Assembly Analysis (RELAX) Gap, 1 Reflood Timelime I Hot Node Node Gap Coefficient, for Canister Canister Coolant Coolant Fission Gas & Hot Node
& Conditions Conditions
~ ~
Analysis Heatup Analysis (HUXY) (HUXY) Peak I Cladding Temperature, Peak Oadding Metal Metal Water Reaction Water Reaction EXEM BWR-2000 Figure 4.1 Flow Diagram for BWR-2000 ECCS Evaluation for Evaluation Model AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 Revision Spectrum Analysis LOCA Break Spectrum Analysis Page 4-14 Page 4-14 [ I] Blowdown Model Figure 4.2 RELAX System Blowdown AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Extended Revision 0 LOCA Break Spectrum Analysis Spectrum Analysis 4-15 Page 4-15 [
]I Figure 4.3 RELAX Hot Channel Blowdown Blowdown Model Top-Peaked Top-Peaked Axial AREVA NP NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Extended Power Uprate Uprate Revision 0 LOCA Break Spectrum Analysis Analysis Page 4-16 Page 4-16 [ I] Figure 4.4 RELAX Blowdown Model RELAX Hot Channel Blowdown Mid-Peaked Axial Mid-Peaked AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 Browns EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Uprate Revision 0 Revision LOCA Break Spectrum Spectrum Analysis Analysis Page 4-174-17 Cross Tie (not credited) LPCS Injection Valve Feedwater Spargers HPCI Turbine Turbine LPCI Injection Core Spray Spargers LPCI Injection Valve Valve Valve Core Break Discharge Discharge Discharge Shutoff Shutoff Valve Valve Valve Recirculation Recirculation Pump Recirculation Pump Recirculation Pump
~ Closed Valve
"- Closed Valve C><J
>K Valve Open Valve Figure 4.5 ECCS Schematic Schematic AREVA NP Inc.
Browns Ferry Units Browns Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Extended Power Uprate Power Uprate Revision 0 LOCA Break Spectrum Spectrum Analysis Analysis Page 4-18 4-18 ((
]I Figure 4.6 Axial Power Distributions at 102%
102% EPU/105% EPUl105% Flow AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Extended Power Uprate Uprate Revision 0 LOCA Break Spectrum Analysis Break Spectrum Analysis Page 4-19 Page 4-19 (( I] Figure 4.7 Axial Power Distributions Distributions at 102% EPU/[ 102% EPu/ [ ] AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Spectrum Analysis Analysis Page 4-20 (( I] Figure 4.8 Axial Power Distribution Distribution at at 102% CL 102% CLTP/105% Flow TP/1 05% Flow AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Spectrum Analysis Page 5-1 5.0 Spectrum Analysis Description Break Spectrum Description The objective analyses is to ensure that the limiting break objective of this LOCA analyses location, break type, break location, break size, and ECCS single single failure are identified. identified. The LOCA response scenario varies varies considerably over the spectrum of break locations. Potential break locations have been considerably separated separated into two groups: groups: recirculation recirculation line breaks and non-recirculation non-recirculation line breaks. The basisbasis for the break locations and potentially potentially limiting single failures analyzed analyzed inin this report is described in the following sections. in 5.1 Limiting Single Failure Limiting Failure Regulatory requirements Regulatory requirements specify that the LOCA analysis be performed performed assuming that all offsite offsite power supplies are lost instantaneously instantaneously and that only safety components safety grade systems and components are available. In In addition, regulatory requirements requirements also specify specify that the most limiting single single failure of ECCS equipment must be assumed assumed in in the LOCA analysis. The term "most limiting" refers to the ECCS equipment equipment failure that produces produces the greatest greatest challenge challenge to event acceptance acceptance criteria. The limiting single single failure can be a common common power supply, an injection valve, a system pump, or system initiation logic. The equipment equipment identified in in the FSAR (Reference (Reference 7) that may produce produce a limiting single failure (SF) is shownshown below:
- Battery Battery power (BATT)
(BATT) 0* Opposite unit false LOCA signal (LOCA) Opposite 0* Low-pressure Low-pressure coolant injection valve (LPCI) (LPCI) 0* Diesel generator (DGEN) Diesel generator (DGEN)
** High-pressure coolant High-pressure coolant injection system (HPCI)
(HPCI) The single failures and the available available ECCS for each failure failure assumed in in this analysis analysis are summarized summarized in in Table 5.1. 5.1. Other potential failures are not specifically specifically considered because they all result in as much or more ECCS capacity. Table 5.1 clearly demonstrates demonstrates that a single failure of the battery results in in the least amount of ECCS capacity and is therefore limiting. ItIt should be be noted that SF-LOCA SF-LOCA and SF-DGEN are identical. identical. 5.2 Recirculation Recirculation Line Breaks The response during a recirculation line LOCA is dependent dependent on break size. ADS operation is an important important emergency system for emergency system for small small breaks. The ADS breaks. The ADS assists assists in in depressurizing depressurizing the the reactor reactor system, and thereby thereby reduces the time required to reach reach rated LPCS and LPCI flow. For large large breaks, rated LPCS and LPCI flow is generally reached before before or shortly after the time when the the AREVA NP Inc.
Browns Ferry Units 1, 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Spectrum Analysis Page 5-25-2 ADS valves open so the ADS system is not required required to mitigate the LOCA. The analyses analyses are performed with six ADS valves in-service. performed in-service. This does not support operation with ADSVOOS. ADSVOOS. Large Large recirculation line break analyses performed for breaks in both the discharge analyses are performed discharge and suction side of the recirculation recirculation pump. It is generally generally expected expected that the pump suction side break will be more severe due to the more rapid blowdown. The two largest flow resistances in the the recirculation piping are the recirculation pump and the jet pump nozzle. For breaks in the the discharge piping, there is a major flow resistance discharge resistance in both flow paths to the break. For breaks breaks in the suction piping, there is only one major flow resistance due to the recirculation pump pump between the break and reactor vessel. As a result, suction side breaks allow the coolant coolant to exit more rapidly and generally generally result in more severe events than discharge discharge side breaks (if(if ECCS ECCS capacity is equal). Both suction suction and discharge discharge recirculation recirculation pipe breaks breaks are considered considered in the the break spectrum spectrum analysis. Two break types (geometries) are consideredconsidered for the recirculation recirculation line break. The two types are are the double-ended double-ended guillotine (DEG) break and the split break. guillotine (DEG) For a DEG break, the piping is assumed to be completely severed severed resulting in two independent independent flow paths to the containment. The DEG break is modeled modeled by setting the break area (at both ends ofof the pipe) equal to the full pipe cross-sectional cross-sectional area and varying varying the discharge discharge coefficient coefficient between 1.0 1.0 and 0.4. The range of discharge coefficients coefficients is used to cover uncertainty in the the geometry at the break. Discharge coefficients below 0.4 are unrealistic and not actual geometry considered in the EXEM BWR-2000 considered BWR-2000 methodology. The most limiting DEG break is determined determined by varying varying the discharge discharge coefficient. A split type break is assumed assumed to be a longitudinal opening or hole in the piping that results in a single break flow path to the containment. Appendix Appendix K K of 10 CFR 50 defines the cross-sectional area of the piping as the maximum maximum split break area area required for analysis. The rate of reactor vessel depressurization depressurization is slower intermediate and small breaks (break slower for intermediate 2 ) compared to area ~< 1.0 ftff) compared large break LOCAs. The HPCI and ADS will assist in reducing the the reactor vessel pressure to the pressure pressure where the LPCI and LPCS flows start. AREVA NP Inc.
Browns Ferry Units 1, 2, and 33 EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 5-3 The break analyses in the intermediate break spectrum analyses intermediate and small break break region consider consider break sizes break sizes between between 1.0 fe ft2 and 0.05 fe. ft2 . Break sizes and single failures are analyzed for both suction and discharge recirculation discharge recirculation line breaks. Section Section 6.0 provides a description intermediate, and small breaks description and result summary for large, intermediate, breaks in the recirculation recirculation line. 5.3 Non-RecirculationLine Breaks Non-Recirculation In addition to breaks in the recirculation recirculation line, breaks breaks in other reactor coolant system piping must considered in the LOCA break spectrum be considered spectrum analysis. Although the recirculation recirculation line large break break results in the largest inventory loss, it does not necessarily largest coolant inventory necessarily result in the most severe challenge to event acceptance acceptance criteria. criteria. The double-ended double-ended rupture of a main steamsteam line is expected to result in the fastest depressurization depressurization of the reactor vessel. Special consideration consideration is required when the postulated postulated break occurs in ECCS piping. Although ECCS piping breaks are small relative to a recirculation pipe DEG break, this break disables an ECCS system and therefore, increases increases the postulated break severity. Table 5.2 summarizessummarizes the available ECCS available ECCS components of the potentially limiting single failures identified components 5.1. The following identified in Table 5.1. following sections address address potential LOCAsLOCAs due to breaksbreaks in non-recirculation non-recirculation line piping. Non-recirculation line breaks outside of the containment Non-recirculation containment are inherently inherently less challenging to fuel limits than breaks inside the containment. For breaks breaks outside containment, isolation or check valve closure will terminate terminate break flow prior to the loss of significant significant liquid inventory inventory and the core covered. If will remain covered. If high-pressure high-pressure coolant inventory inventory makeup cannot be reestablished, reestablished, ADS ADS actuation may become necessary. [
] Although analyses of breaks outside containment containment may be required to address address non-fuel requirements, these breaks related regulatory requirements, breaks are not limiting relative to fuel acceptance acceptance criteria criteria such as PCT.
5.3.1 Breaks HPCI Line Breaks [ AREVA AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Spectrum Analysis Spectrum Analysis Page 5-4 5-4
]I The HPCI injection line is connected connected to the feedwater feedwater line outside of the containment.
((
))
5.3.2 LPCS Line Breaks Breaks A break break in the LPCS line is expected to have many characteristics characteristics similar to [
] However, some characteristics characteristics of the LPCS line break are unique and are not addressed addressed in other LOCA analyses. Two important important differences differences from other LOCA LOCA analyses analyses are that the break flow will exit from the region inside the core shroud and the break break will disable one one LPCS system. The LPCS line break is assumedassumed to occur just outside the reactor vessel. ((
]I 5.3.3 LPCI Line Breaks Breaks The LPCI injection injection lines are connected connected to the larger recirculation discharge discharge lines. ((
]I 5.3.4 Breaks Main Steam Line Breaks A steam line break inside containment is assumed assumed to occur between between the reactor reactor vessel and the the inboard main steam line isolation valve (MSIV) upstream of the flow limiters. The break results in high steam flow out of the broken line and into the containment. Prior to MSIV closure, a steam line break also results in high steam steam flow in the intact intact steam lines as they feed the break via the steam line manifold. A steam steam line break inside containment results in a rapid inside containment rapid depressurization depressurization of the reactor reactor vessel. Initially the break flow will be high quality steam; however, the rapid depressurization produces a water level swell that results in liquid discharge depressurization produces discharge AREVA NP Inc.
Browns Ferry Units 1, 1,2, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Spectrum Analysis 5-5 Page 5-5 because it results in at the break. For steam line breaks, the largest break size is most limiting because the most level swell and liquid loss out of the break. [
]
5.3.5 Feedwater Line Breaks Feedwater Breaks ((
]
5.3.6 Breaks RCIC Line Breaks The RCIC discharges feedwater line, [ discharges to the feedwater
]
The steam steam supply to the RCIC turbine comes from the main steam line from the reactor vessel; ((
))
AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Revision 0 LOCA Break Spectrum Spectrum Analysis Analysis Page 5-6 5-6 5.3.7 RWCU Breaks RWCU Line Breaks The RWCU RWCU extraction connected to a recirculation suction line with an additional extraction line is connected vessel bottom head. (( connection to the vessel connection
]
feedwater line break. The RWCU return RWCU return line is less limiting than aa feedwater A break in the RWCU line is connected to the feedwater line; ((
))
5.3.8 5.3.8 Line Breaks Instrument Line Instrument Breaks (( I] AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Spectrum LOGA Analysis Spectrum Analysis 5-7 Page 5-7 Table 5.1 ECCS Single Failure Systems Systems Assumed Assumed Remaining Remaining Failure Recirculation* Recirculation Recirculation* Recirculation Suction Break Discharge Break Break Battery Battery ADS,t 1 LPCS,:J: LPCS,l 2 LPCI§ ADS, ADS,11 LPCS LPCS Opposite unit false LOCA signal ADS, HPCI, 1 LPCS, 2 LPCI ADS, HPCI, 1 LPCSLPCS LPCI injection valve ADS, HPCI, HPCI, 2 LPCS, 2 LPCI ADS, HPCI, 2 LPCSLPCS Diesel generator ADS, HPCI, HPCI, 1 LPCS, 2 LPCI ADS, HPCI, 1 LPCSLPCS HPCI ADS, 2 LPCS, 4 LPCI** ADS, 2 LPCS, 2 LPCI ADS,2
- Systems remaining, as identified in this table for recirculation Systems recirculation suction line breaks, are applicable applicable to other non-ECCS non-EGGS line breaks. For a LOGALOCA from an ECCS EGGS line break, the systems remaining are those listed for recirculation recirculation suction breaks, less the ECCS EGGS in which the break break is assumed.
tt Analyses are performed with all six ADS valves in-service. Analyses are performed with all six ADS valves in-service.
- j:
LPCS means Each LPGS means operation of two core spray pumps pumps in aa system. ItIt is assumed assumed that both pumps in in a system must operate operate to take take credit for core spray spray cooling or inventory inventory makeup makeup in that loop. §
§ Two LPCI LPGI pumps into one loop. ** Four LPGI LPCI pumps into two loops, two per loop.
AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Uprate Revision Revision 0 LOCA Break Spectrum LOGA Analysis Spectrum Analysis 5-8 Page 5-8 5.2 Available ECCS for Table 5.2 for ECCS ECCS Line Break LOCAs LOCAs ECCS Line Single Available Available Break Failure Failure ECCS ECCS Battery 2 LPCI,* ADSt ADSt False LOCA signal 2 LPCI, HPCI, ADSADS LPCS LPCI valve LPCS,' HPCI, ADS 2 LPCI, 1 LPCS,:t: ADS Diesel generator generator 2 LPCI, HPCI, ADSADS HPCI system 4 LPCI,§ 1 LPCS, ADSADS Battery Battery 1 LPCS, ADSADS False False LOCA signal 1 LPCS, HPCI, HPCI, ADS ADS LPCI LPCI valve 2 LPCS, HPCI, HPCI, ADS ADS Diesel generator 1 LPCS, HPCI, HPCI, ADS ADS HPCI HPCI system 2 LPCI, 2 LPCS, ADS ADS Battery 2 LPCI, 1 LPCS, ADS ADS False LOCA signal 2 LPCI, 1 LPCS, ADS ADS HPCI LPCI valve 2 LPCI, 2 LPCS, ADS ADS generator Diesel generator 2 LPCI, 1 LPCS, ADS ADS HPCI system 4 LPCI, 2 LPCS, ADS ADS Two LPCI pumps into one Two LPGI pumps into one loop. loop. tt Analyses Analyses are performed with are performed all six with all six ADS valves in-service. ADS valves in-service. LPCS means operation of two core spray pumps in a system. It is assumed that both pumps in Each LPGS a system system must operate to take credit for core spray cooling cooling or inventory inventory makeup in that loop. §
§ LPCI pumps into two loops.
Four LPGI AREVA NP Inc.
Browns Ferry Units 1, 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 6-1 6.0 Recirculation Line Break Recirculation Break LOCA AnalysesAnalyses The largest largest diameter recirculation system pipes are the suction line between diameter recirculation between the reactor vessel recirculation pump and the discharge and the recirculation discharge line between between the recirculation pump and the riser analyses are performed manifold ring. LOCA analyses performed for breaks in both of these locations with consideration consideration for both DEG and split break break geometries. The breakbreak sizes considered considered included DEG breaks breaks with discharge discharge coefficients from 1.0 1.0 to 0.4 and split breaks with areas ranging between the full pipe area ft2 . As discussed area to 0.05 ft2. discussed in Section Section 5.0, the single failures considered considered recirculation line break analyses in the recirculation analyses are SF-BATT, SF-LOCA, SF-DGEN, SF-HPCI, and SF-DGEN, SF-HPCI, SF-LPCI. [ 1 6.1 Break Analysis Results Limiting Break 2 analyses demonstrates The analyses demonstrates thatthat the (highest PCT) limiting (highest the limiting line break recirculation line PCT) recirculation is the break is 0.5 ft2 the 0.5 ft split break in the pump discharge discharge piping with an SF-BATT single failure and a mid-peaked mid-peaked axial power shape when operating operating at 102% 102% EPU and 105% 105% rated core flow. The PCT is 1998°F. The The key results and event times for this limiting break are provided provided in Tables Tables 6.1 and 6.2, respectively. Figures 6.1 - 6.26 provide plots of key parametersparameters from the RELAX system and hot channel channel blowdown blowdown analyses. A plot of cladding temperature temperature versus time in the hot assembly from the HUXY heatup heatup analysis is provided in Figure 6.27. Tables 6.3 - 6.8 present present the detailed detailed break spectrum POT results for each of the single failures failures considered in this LOCA analyses. Table 6.9 provides a summary and state points considered summary of thethe highest highest PCT recirculation recirculation line break break calculations for each of the single failures, state points, and power shapes. The results of the break analyses are discussed axial power discussed in the following sections. [ AREVA NP Inc.
Browns Ferry Units 1, 2, andand 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Uprate Revision 0 LOCA Break Spectrum Spectrum Analysis Analysis Page 6-2 6-2
]
6.2 Break Location Location Analysis Results Table 6.9 shows that the maximum maximum PCT calculated calculated for a recirculation line break occurs in the the discharge piping. pump discharge 6.3 Break Break Geometry Geometry and Size Analysis Results Recirculation line break PCT results versus break geometry Recirculation geometry (DEG or split) and size are presented in Tables 6.3 - 6.8. The maximum presented calculated for a recirculation line break maximum PCT calculated occurs ft 2 split break. occurs for a 0.5 ft2 6.4 Limiting Limiting Single-Failure Single-FailureAnalysis Results As mentioned in Section 5.1, 5.1, SF-BATT is the limiting single failure available ECCS failure based on available ECCS capacity. This conclusion is supported by analyses performed for SF-LOCA, SF-LPCI, analyses performed SF-LPCI, SF-DGEN, and SF-HPCI 0.5 ff ft2 breaks breaks as reported in Tables 6.4 - 6.6. 6.5 Axial Power Power Shape Analysis Results The results in Table 6.9 show that the mid-peaked mid-peaked axial power power shape is limiting compared compared to the the top-peaked top-peaked shape analyses for the limiting break size. 6.6 State Point PointAnalysis Table Table 6.9 shows that 102% 102% EPU and 105% 105% rated core flow was the limiting state point for the the recirculation line breaks. Both [ ] and 102% 102% CLTP CLTP were less limiting. limiting. AREVA NP Inc.
and 3 Browns Ferry Units 1, 2, and EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Spectrum Analysis Page 6-3 6-3 Table 6.1 Results for Limiting Limiting TLO Recirculation Recirculation Line Break ft22 Split Pump Discharge SF-BATT 0.5 ft SF-BATT Mid-Peaked Axial 102% Mid-Peaked 102% EPU 105% 105% Flow peT PCT 1998 0 F Maximum Maximum local MWR 1.83% 1.83% Maximum planar average Maximum MWR average MWR 0.839% AREVA NP Inc.
Browns Ferry 1,2, Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Extended Power Uprate Uprate Revision 0 Revision LOCA Break Spectrum Analysis Page 6-4 Event Times for Limiting Table 6.2 Event Limiting TLO Recirculation Recirculation Line BreakBreak 0.5 ft22 Split Pump Discharge 0.5 ft Discharge SF-BATT Mid-Peaked Mid-Peaked Axial 102% 102% EPU 105%105% Flow Time Time Event (sec) Initiate break 0.0 0.0 Initiate scram 0.5 0.5 Low-low liquid level, L2 (448 in) 16.4 16.4 Low-low-low liquid level, Low-low-low level, L Li1 (372.5 in) 26.7 26.7 Jet pump uncovers uncovers 35.5 Recirculation suction Recirculation suction uncovers 57.2 Lower plenum flashes 71.3 71.3 LPCS high-pressure high-pressure cutoff 201.4 201.4 LPCS valve pressure permissive 193.1 LPCS valve starts to open open 195.1 LPCS valve fully open 228.1 LPCS permissive for ADS timer 55.7 55.7 LPCS pump at rated speed 58.7 58.7 LPCS flow starts 201.4 201.4 RDIV pressure permissive 222.0 RDIV starts to close 224.0 RDIV fully closed 260.0 260.0 Rated LPCS flow 277.2 ADS valves open 175.7 175.7 Blowdown ends 277.2 Bypass reflood 421.4 421.4 Core Core reflood 358.3 358.3 PCT 358.3 358.3 AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Extended Revision 0 LOCA Break Spectrum Analysis Spectrum Analysis Page 6-5 6-5 Table 6.3 TLO Recirculation Line Break Spectrum Results TlO Recirculation Results 102% EPU 105% Flow SF-BATT for 102% [
]I
- [
I] AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 Browns EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Revision 0 Spectrum Analysis LOCA Break Spectrum Analysis Page 6-6 Page 6-6 Recirculation Line Break Spectrum Table 6.4 TLO Recirculation Spectrum Results Results for 102% SF-LOCA/DGEN 102% EPU 105% Flow SF-LOCAlOGEN [II
]I AREVA AREVA NP Inc.
Browns Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Power Uprate Revision Revision 0 Spectrum Analysis LOCA Break Spectrum Analysis Page Page 6-7 6-7 Table 6.5 TLO Recirculation Recirculation Line Break Spectrum Spectrum Results Results 102% EPU 105% Flow SF*HPCI for 102% SF-HPCI [I
]I AREVA NP Inc.
Browns Ferry Units Browns Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Extended Revision Revision 0 Spectrum Analysis LOCA Break Spectrum Analysis Page Page 6-8 6-8 Recirculation Line Break Spectrum Table 6.6 TLO Recirculation Results Spectrum Results 102% EPU 105% Flow SF-LPCI for 102% I [ 1 AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 Browns EMF-2950(NP) EMF-2950(NP) Extended Power Power Uprate Uprate Revision 0 Revision LOCA Break Spectrum Analysis Break Spectrum Analysis Page 6-9 Table 6.7 TLO Recirculation Spectrum Results Recirculation Line Break Spectrum Results 102% EPU [ for 102% ] SF-BATT [I I]
- [
]I AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Extended Power Power Uprate Uprate Revision 0 Revision LOCA Break Spectrum Analysis Break Spectrum Analysis Page 6-10 6-10 Table 6.8 TLO Recirculation Recirculation Line Break Spectrum Spectrum Results Results 102% CLTP 105% Flow SF-BATT for 102% [
]I AREVA NP Inc.
Units 1, 2, and 3 Browns Ferry Units Browns EMF-2950(NP) EMF-2950(NP) Extended Power Extended Uprate Power Uprate Revision 0 Revision LOCA Break Spectrum Analysis Break Spectrum Analysis Page 6-11 TLO Summary of TlO Table 6.9 Summary Recirculation Results Recirculation Line Break Results Cases Highest PCT Cases ((
]I AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) . EMF-2950(NP) Extended Extended Power Power Uprate Uprate Revision 0 Break Spectrum Analysis LOCA Break Analysis Page 6-12 6-12 [ I] Recirculation Line Break Figure 6.1 Limiting TLO Recirculation Break Plenum Pressure Upper Plenum [I I] Recirculation Line Break Figure 6.2 Limiting TLO Recirculation Break Total Break Rate Break Flow Rate AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Extended Power Uprate Uprate Revision 0 Analysis LOCA Break Spectrum Analysis Page 6-13 6-13 [
]I Recirculation Line Break Figure 6.3 Limiting TLO Recirculation Core Inlet Flow Rate I[
]I Figure 6.4 Limiting TLO Recirculation Line Break Rate Core Outlet Flow Rate AREVA AREVA NP Inc.
Browns Ferry Units Browns Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Extended Power Uprate Power Uprate Revision Revision 0 LOCA Break Spectrum Analysis Analysis Page 6-14 6-14 [
]I Figure 6.5 Limiting TLO Recirculation Line Break Intact Loop Jet Pump Drive Flow Rate Rate
((
]I Figure 6.6 Limiting TLO Recirculation Recirculation Line Break Intact Loop Jet Jet Pump Suction Flow Rate Rate AREVA NP Inc.
Browns Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Revision 0 Revision LOCA Break Spectrum Spectrum Analysis Analysis Page 6-15 6-15 [I I] Figure 6.7 Limiting TLO Recirculation Recirculation Line Break Break Intact Intact Loop Jet Jet Pump Exit Flow Rate [I
]I Figure 6.8 Limiting Limiting TLO Recirculation Recirculation Line Break Broken Broken Loop Jet Pump Drive Flow RateRate AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Break Spectrum Analysis Analysis Page 6-16 6-16 ((
]I Figure 6.9 Limiting TLO Recirculation Line Break Broken Broken Loop Jet Jet Pump Suction Flow Rate
((
]I Recirculation Line Break Figure 6.10 Limiting TLO Recirculation Break Broken Loop Jet Pump Exit Flow Rate Broken AREVA AREVA NP Inc.
Browns Ferry Units Browns Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Power Uprate Revision 0 LOCA Break Spectrum Spectrum Analysis Analysis Page 6-17 6-17 0.-~B~R~O~W~NS~F~ERrR~Y_O~,~S~FrT~2~P~D-TMI~D~S~F_-B~ArT~T~10~2~P/~1~0~S~F~ETP~U
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g 00 10O0 200 300 400 500 600 700 00 100 200 300 400 500 600 700 800 TIME (SEC) (SEC) Figure 6.11 Limiting TLO Recirculation Recirculation Line Break Bn eak ADS Flow Rate BROWNS FERRY 0.5 BROWNS 0,5 FT2/PD FT2/PD MID SF-BATT SF -BA TT 1102P/105F 02P /1 OSF EPU uD LO uw V) Cq w V1 "2-0 CD LCo
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Browns Ferry Units 1, 2, and Browns and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Spectrum Spectrum Analysis Analysis 6-18 Page 6-18 o BROWNS FERRY o.s FT2 PO MID SF -BA TT 102P 10SF EPU
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TIME (SEC) Figure 6.13 6.13 Limiting Recirculation Line Break Limiting TLO Recirculation Break LPCS Flow Rate Rate BROWNS FERRY FERRY 0.5 FT2/PD FT2/PD MID SF SF-BATT 02P / 1OSF EPU
-BA TT 1102P/105F 1L-0 r)
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Browns Ferry Units 1, 2, and 3 Browns EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Revision Revision 0 LOCA Break Spectrum Spectrum Analysis Analysis 6-19 Page 6-19 BROWNS BROWNS FERRY FERRY 0.5 FT2/PD MID SF SF-BATT
-BA TT 1 102P/105F 02P /1 05F EPU I I I I I n
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TIME (SEC) Figure 6.16 Limiting TlO Recirculation Line Break TLO Recirculation Break Upper Downcomer Upper Downcomer Mixture level Level AREVA NP Inc. Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Spectrum Analysis Analysis' Page Page 6-20 6-20 BROWNS FERRY O.S FT2/PD MID SF-BATT 102P/10SF EPU UD
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~8 0'"
CO 0() 100 100 200 200 300 300 400 400 500 500 600 700 800 BOO TIME (SEC) TIME (SEC) Figure 6.18 Limiting TLO Recirculation Recirculation Line Break Lower Downcomer Downcomer Liquid Liquid Mass Mass AREVA NP Inc.
Ferry Units 1, 2, and 3 Browns Ferry EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Spectrum Analysis Analysis Page 6-21
~ BROWNS FERRY 0.5 FT2 PD MID SF -BA TT 102P 105F EPU mo
-/1
<0 M0
_o La I
-i 0
00 0() 100 200 300 300 400 500 600 700 700 800 BOO TIME (SEC) (SEC) Recirculation Line Break Figure 6.19 Limiting TLO Recirculation Intact Discharge Line Liquid Mass Intact Loop Discharge Mass 88 0 0 BROWNS FERRY 0.5 FT2/PD FT2/PD MID SFSF -BA TT 102P /1 05F EPU 0 0 3:8 0 0 CD
...J
~o vi~
o 0 " UlDo
<{00 08 58 0'"
zoo
- J
;:)0 zo Wo
...Jt<l 0-0.
0:::
~8 0.0
;:)~
co 0() 100 100 200 300 300 400 500 600 600 700 800 BOO (SEC) TIME (SEC) Figure 6.20 Limiting TLO Recirculation Recirculation Line Break Upper Plenum Liquid Mass Upper Mass AREVA NP Inc.
Browns Browns Ferry Units Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Power Uprate Revision Revision 0 LOCA Break Spectrum Spectrum AnalysisAnalysis Page 6-22 8g BROWNS FERRY 0.5 FT2 PD MID SF -BA TT 102P 105F EPU 0 no
.Zo wo 05 w*
Ld g00 o~ 0 __ ~ ____ ~ ____ ~ ____ ~ ____ ~ __ ~ ____ ~ ____ ~ Ro 100 100 200 200 300 300 400 500 500 600 700 BOO 800 TIME (SEC) (SEC) Figure 6.21 Limiting TLO Recirculation Recirculation Line Break Break Lower Plenum Liquid Mass Mass BROWNS FERRY 0.5 FT2 BROWNS FT2/PD PD MID SF-BATT 102P/105F SF -BA TT 102P 105F EPU I I I I I 3i o 0
-LJo 1-0<
W
-j
~~
z I U 00 I-00 I 1H o~ __ ~ ____ ~ ____ ~ ____ ~ ____ ~ __ ~ ____ ~ ____ ~ IB 50 5B 100 lBB 15 15B 200 250 300 350 400 400 (SEC) TIME (SEC) Figure 6.22 Limiting TLO Recirculation Recirculation Line Break Hot Channel Inlet Flow Rate Rate AREVA AREVA NP Inc.
Browns Ferry Units Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Power Uprate Revision 0 Revision Spectrum Analysis LOCA Break Spectrum Analysis Page 6-23 6-23 BROWNS FERRY oo~~~~~=r~~~~~F-~~~~=+~~~--~ o.s FT2/PD MID SF -BA TT 1 02P /1 OSF EPU
~.,
~
Oo o ro.. ... U W U1 m
--l
~o 0
-j U-2 z
z 10 70L-------'-SO-----,LOO-----"SO-----2LOO------'2S-0----3.LOO----.....13S-0-------'400 400 TIME (SEC) Figure 6.23 Limiting TLO Recirculation Recirculation Line Break Break Hot Channel Outlet Flow Rate Rate [
]I Figure 6.24 Limiting TLO Recirculation Recirculation Line Break Break Hot Channel Coolant Coolant Temperature Temperature at the Limiting Node Node AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 Browns EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Revision Revision 0 LOCA Break Spectrum Analysis Spectrum Analysis Page 6-24 [ I] Figure 6.25 Limiting TLO Recirculation Recirculation Line Break Break Channel Quality at the Limiting Node Hot Channel Node [I
]I Recirculation Line Break Figure 6.26 Limiting TLO Recirculation Hot Channel Channel Heat Transfer Transfer Coef. at the Limiting Node Node AREVA NP Inc.
Browns Ferry Units Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Power Uprate Revision Revision 0 LOCA Break Spectrum Spectrum Analysis Analysis Page 6-25 6-25 2500 o---a PCT Rod (Rod 11) 0----0 Water Channel IJr-------{>. Fuel Channel 2000 g Q) L
- J 0
1500 L Q) CIL a. E Q) F-- l-on e> 1000 1000 c
'6
-0 0
(30 500 500 a 50 100 150 150 200 250 300 300 350 350 400 Time (sec) Figure 6.27 Limiting TLO Recirculation Recirculation Line Break Cladding Temperatures Cladding Temperatures AREVA AREVA NP Inc.
Browns Ferry Units 1, 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Spectrum Analysis Page 7-1 7.0 Non-Recirculation Line LOCA Analysis Non-Recirculation Analysis LOCA analyses performed for breaks analyses are performed breaks in the LPCS line only. Breaks in other non-recirculation lines are less limiting for the reasons discussed discussed in Section 5.3. Note that for LPCS LPCS line break cases with no core spray available, the HUXY HUXY heatup analysis is performed performed with thethe core spray heat heattransfer transfer coefficients equal to 0.0. 7.1 Limiting ECCS Limiting ECCS Line BreakBreak Results The results of this analysis indicate that the limiting ECCS line break is the 0.4 if analysis indicate ft2 DEG break in the LPCS line with battery power failure and a top-peaked axial power power shape. The initial operating conditions for the limiting case are 102% 102% rated core power power and 105% 105% rated core flow. The PCT for the limiting limiting ECCS line break break is 1604'F 1604°F and maximum local cladding oxidation is 0.26%. The key event times for the limiting breakbreak are provided in Table 7.1. 7.1. Table 7.2 presents presents initial independent PCT results for the ECCS line breaks. (( condition flow independent
] The The 1604'F 1604 of maximum PCT for ECCS line breaks breaks is lower than the maximum PCT for recirculation recirculation line breaks breaks of 1998°F. Therefore, ECCS line breaks are nonlimiting.
AREVA AREVA NP Inc.
Ferry Units 1, 2, and 3 Browns Ferry EMF-2950(NP) EMF-2950(NP) Extended Extended Power Uprate Uprate Revision 0 Revision LOCA Break Spectrum Spectrum Analysis Page 7-2 Table 7.1 Event Times for LimitingLimiting ECCS Line Break Break ftl2 Double-Ended 0.4 ft Double-Ended Guillotine Guillotine SF-BATT Top-Peaked Axial 102% Top-Peaked 102% EPU 105%105% Flow Time Time Event (sec) Initiate break 0.0 0.0 Initiate scram scram 0.5 0.5 Low-low Low-low liquid level, (448 in) level, L2 (448 in) 27.3 Low-low-low Low-low-low liquid level, LI in) L 1 (372.5 in) 77.9 Jet pump uncovers 82.7 82.7 Recirculation suction uncovers uncovers 0.0 0.0 Lower plenum flashes 55.9 55.9 high-pressure cutoff LPCI high-pressure 205.2 LPCI valve pressure permissive 191.7 191.7 LPCI valve starts to open 193.7 193.7 LPCI valve fully open 233.7 LPCS permissive for ADS timer 106.9 106.9 LPCI pump at rated speed 110.9 110.9 LPCI flow starts 208.7 pressure permissive RDIV pressure 264.0 264.0 RDIV starts to close 266.0 RDIV fully closed 302.0 302.0 Rated LPCS pressure pressure 320.8 ADS valves open 226.9 226.9 Blowdown Blowdown ends 320.8 Bypass Bypass reflood NA Core reflood 347.4 PCT 347.4 AREVA NP Inc.
Browns Browns Ferry Units Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Extended Uprate Power Uprate Revision 0 Revision Spectrum Analysis LOCA Break Spectrum Analysis 7-3 Page 7-3 Table 7.2 Non-Recirculation Non-Recirculation Line Break 102% EPU Spectrum Results for 102% I[ I] AREVA NP Inc.
Browns Ferry Units 1,1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Revision 0 Revision Spectrum Analysis LOCA Break Spectrum Page 8-1 8.0 Operation LOCA Analysis Single-Loop Operation Single-Loop Analysis During SLO the pump in one recirculation loop is not operating. A break may occur in either similar to those from a two-loop loop, but results from a break in the inactive loop would be similar operation break. If operation occurs in the inactive loop during SLO, the intact active loop flow to If a break occurs the reactor vessel would continue during recirculation pump coastdown period and would during the recirculation would provide core cooling similar to that which would occur in breaks during provide during two-loop operation. response would be similar System response equal-sized break during two-loop similar to that resulting from an equal-sized operation. A break in the active loop during SLO results in a more operation. more rapid loss of core flow and earlier degraded core conditions relative to those from a break earlier degraded break in the inactive loop. Therefore, only breaks in the active recirculation loop are analyzed. analyzed. active recirculation loop during SLO will result in an earlier loss of core heat A break in the active transfer relative to a similar break occurring during two-loop operation. This occurs because occurring during because there will be an immediate loss of jet pump drive flow. Therefore, Therefore, fuel rod surface surface temperatures temperatures operation LOCA. Also, the early loss of increase faster in an SLO LOCA relative to a normal operation will increase transfer will result in higher stored energy in the fuel rods at the start of the heatup. core heat transfer The increased severity of an SLO LOCA can be reduced increased severity reduced by applying applying an SLO multiplier to the the two-loop MAPLHGR limits. (( two-loop MAPLHGR
]
8.1 8.1 SLO Analysis Modeling Methodology SLO Analysis Modeling Methodology [
]
AREVA NP Inc.
Browns Ferry Units Browns Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Power Uprate Revision 0 Revision LOCA Break Spectrum Spectrum Analysis Analysis 8-2 Page 8-2 [ I] 8.2 SLO SLO Analysis Results [ [I
]
The SLO analyses analyses are performed performed with aa 0.85 multiplier multiplier applied to the two-loop MAPLHGR MAPLHGR limit limit resulting in an SLO MAPLHGR MAPLHGR limit of 10.625 kW/ft. The analyses are performed performed at BOL ATRIUM-10 ATRIUM-10 fuel conditions. The limiting SLO LOCA is the 0.6 ft ft22 split pump discharge line break with SF-BATT SF-BATT and a mid-peaked mid-peaked axial power shape. The PCT for this case is 1818°F. 1818'F. Other Other key results and event times for the limiting SLO LOCA are providedprovided in Tables Tables 7.1 and 7.2, respectively. Figures 7.1 - 7.26 show important important RELAX RELAX system blowdown and hot channel results from the SLO limiting LOCA analysis. Figure 7.27 shows the cladding surface surface temperature temperature for the limiting rod as calculated calculated by HUXY. HUXY. Table Table 7.3 shows the spectrum spectrum of SLO analyses and the PCT for each each case. A comparison comparison of the limiting SLO and the limiting two-loop results is provided provided in Table 7.4. The results in in Table Table 7.4 show that the limiting two-loop LOCA results bound the limiting SLO results when a 0.85 multiplier multiplier is applied to the two-Io'op two-loop MAPLHGR MAPLHGR limit. AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Spectrum Analysis Analysis Page 8-3 Table 8.1 Results for Limiting Limiting SLO Recirculation Line Break Recirculation tt2 Split Pump Discharge 0.6 ft Discharge SF-BATT Mid-Peaked Axial [ Mid-Peaked ]I peT PCT 1818OF Maximum Maximum local MWR 0.91% 0.91% AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Uprate Extended Power Uprate Revision 0 LOCA Break Break Spectrum Analysis 8-4 Page 8-4 Table 8.2 Event Event Times for Limiting SLO Recirculation Line Break Recirculation 0.6 ft22 Split Pump Discharge 0.6 ft Discharge SF-BATT SF-BATT Mid-Peaked Axial (( Mid-Peaked ] Time Time Event (sec) Initiate break break 0.0 0.0 Initiate scram 0.5 0.5 Low-low liquid level, L2 (448 in) 14.6 14.6 Low-low-low liquid level, LLi1 (372.5 in) Low-low-low in) 22.4 22.4 Jet pump uncovers uncovers 30.4 30.4 Recirculation suction uncovers Recirculation uncovers 47.0 Lower plenum flashes 60.5 60.5 LPCS high-pressure high-pressure cutoff 185.9 185.9 LPCS valve pressure permissive permissive 177.8 177.8 LPCS valve starts to open 179.8 179.8 LPCS valve fully open 212.8 212.8 LPCS permissive for ADS timer 51.4 51.4 LPCS pump at rated speed 54.4 LPCS flow starts 185.9 185.9 RDIV pressure permissive 205.3 205.3 RDIV starts to close 207.3 RDIV fully closed 243.3 Rated LPCS flow 255.0 ADS valves open 171.4 171.4 Blowdown ends 255.0 Bypass reflood 389.9 Core reflood 335.0 PCT 335.0 335.0 AREVA AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Uprate Revision Revision 0 LOCA Break Spectrum Analysis Spectrum Analysis Page 8-5 8-5 Table 8.3 SLO Recirculation Recirculation Line Line Spectrum Results Break Spectrum Results [I
]
- [
I] AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Spectrum Analysis Spectrum Analysis Page 8-6 Table 8.4 Single- and Two-Loop Operation PCT Summary Two-Loop Operation Limiting PCT Operation Operation Case (OF) (OF) Single-loop Single-loop ft2 split pump discharge 0.6 ft2 discharge 1818 1818 mid-peaked mid'"peaked SF-BATT Two-loop ft22 split pump discharge 0.5 ft discharge 1998 1998 mid-peaked mid-peaked SF-BATT AREVA AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF~2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision a 0 Analysis LOCA Break Spectrum Analysis Page 8~7 8-7 [
]I Figure 8.1 Limiting SLO Recirculation Recirculation Line Break Upper Plenum Pressure Upper Plenum
[
]I Figure 8.2 Limiting SLO Recirculation Recirculation Line Break Break Total Break Flow Rate AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Revision 0 Revision LOCA Break Spectrum Spectrum Analysis Analysis 8-8 Page 8-8 [ I] Figure 8.3 Limiting SLO Recirculation Recirculation Line Break Break Core Inlet Flow Rate [ I] Figure Figure 8.4 Limiting Recirculation Line Break Limiting SLO Recirculation Break Core Outlet Flow Rate Rate AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Extended Power Uprate Uprate Revision Revision 0 Analysis LOCA Break Spectrum Analysis Page Page 8-9 8-9 [ I] Figure 8.5 Limiting SLO Recirculation Recirculation Line Break Intact Intact Loop Jet Pump Drive Flow Rate [I I] Recirculation Line Break Figure 8.6 Limiting SLO Recirculation Break Intact Loop Jet Pump Suction Flow Rate AREVA NP Inc.
Browns Ferry Units 1, 2, and and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Uprate Revision 0 LOCA Break Spectrum Analysis Spectrum Analysis Page 8-10 8-10 [ I] Figure 8.7 Limiting SLO Recirculation Recirculation Line Break Break Intact Loop Jet Pump Exit Flow Rate [I
]I Figure 8.8 Limiting SLO Recirculation Recirculation Line Break Broken Loop Jet Broken Jet Pump Drive Flow Rate AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Spectrum Analysis Spectrum Analysis Page 8-11 8-11 [ I] Figure Figure 8.9 Limiting SLO Recirculation Recirculation Line Break Break Broken Broken Loop Loop Jet Pump Pump Suction Flow Rate ((
]I Figure 8.10 Limiting SLO Recirculation Recirculation Line Break Broken Loop Jet Pump Exit Flow Rate Rate AREVA NP Inc.
Browns Ferry Units Browns Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Power Uprate Revision 0 Revision Spectrum Analysis LOCA Break Spectrum Analysis Page 8-12 8-12 o~ r-----,B=.R.:..:;O...:..:W.:..:.NS=---.cF-=.ER:.;:R.:..:Y--=.;0.c.=.6--,F,..:.T-=.2<....:P-=D~MI:.=.D--,S:..:.F_-=.cBATCTc.:.T--'-C10:..::2::"PL.:..:.1O:..::S.:..:.F-=S:;:L-=O-=E:::..P-=U~ C-,F mo uw (I) mo
....10
?Ii oC0 C',
....I
"-0 o (I)'"
o g II I I 0O 0() 100 100 200 300 300 400 400 500 600 700 BOO 800 TIME (SEC) (SEC) Figure 8.11 8.11 Limiting SLO SLO Recirculation Recirculation Line Break ADS Flow Rate Rate BROWNS BROWNS FERRY FERRY 0.6 FT2/PD FT2/PD MID SF-BATT 102P/10SF 102P/105F SLO EPU I I I I I I I U') uLi w (I) m do
?Ii o0
....I
-I uC3) a.
- c
" , L -_ _~_ _ _ _-L____- L____~____L -__~____-L____~
10 10 100 100 200 200 300 300 400 400 500 500 600 600 700 700 800 BOO TIME (SEC) (SEC) Figure 8.12 8.12 Limiting SLO Recirculation Recirculation Line Break HPCI Flow Rate AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF~2950(NP) EMF-2950(NP) Extended Uprate Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Analysis 8-13 Page 8-13 o BROWNS tbIUWNS FERRY L.NKY 0.6 U.b FT2 PD MIU V I Z/ FU MID SF -BA TT Z>V-bA 102P /1IU:I-II I1UZI'~/ 05F SLO bLU EPU LI-
~
o o U')~ U') LO
~
-j 0
g 0 00 0() 100 100 200 200 300 300 400 400 500 500 600 600 700 700 Boo BOO TIME (SEC) (SEC) Figure 8.13 Limiting SLO SLO Recirculation Recirculation Line Break LPCS Flow Rate Rate BROWNS FERRY FERRY 0.6 FT2/PD FT2/PD MID SF SF-BATT
-SA TT 1102P/105F 02P /1 05F SLO EPU EPU 0
EL IAI I
'"I
*0 100 200 300 I I I I
'70 100 200 300 400 500 500 600 700 800 BOO (SEC)
TIME (SEC) Figure 8.14 Limiting SLO Recirculation Line Break Figure 8.14 Limiting Recirculation Break Intact Loop Loc*p LPCI Flow Rate AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Extended Power Uprate Uprate Revision 0 LOCA Break Spectrum Analysis Analysis Page 8-14 Page 8-14 BROWNS SF -BA TT 102P/105F BROWNS FERRY 0.6 FT2/PD MID SF-BATT 102P /1 05F SLO EPU LOn u~ w (f)
"I)
(D
.0 3:
o 0
...J u...
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...J
...J (D
N 1
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10 100 200 300 300 400 500 600 700 700 Boo BOO TIME (SEC) (SEC) Figure 8.15 Limiting Recirculation Line Break Limiting SLO Recirculation Broken Loop LPCI Flow Rate BROWNS FERRY 0.6 FT2/PD MID SF-BATT 102P/105F SLO EPU
-J U-U-
....i w
of
~'"
-S W
w LL
...J X
-IJ
~
a::'" Q:2= w o 0 o 0 z
~"'
0 o a:: aN-w a 0. g,N
-0 100 200 300 400 cO 100 200 300 400 500 600 700 800 BOO TIME (SEC)
(SEC) Figure 8.16 Limiting SLO Recirculation Recirculation Line Break Upper Downcomer Mixture Level Upper Downcomer AREVA NP Inc.
Browns Browns Ferry Units Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Extended Uprate Power Uprate Revision Revision 0 LOCA Break Break Spectrum Analysis Analysis 8-15 Page 8-15 BROWNS FERRY 0.6 FT2/PD MID SF -BA TT 102P /1 05F SLO EPU X (0 3-J x bw 0 0 c() 00 100 100 200 300 300 400 TIME (SEC) TIME (SEC) 500 600 600 700 800 BOO Figure Figure 8.17 Limiting SLO Recirculation Line Break Break Lower Downcomer Lower Downcomer Mixture Mixture Level Level o 8g BROWNS BROWNS FERRY FT2/P0 MID SF-FERRY 0.6 FT2/PD SF-BATT 102P/105F SLO EPU
<0- '"
o g o [jJ-m8
-=- *0
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aw 00 000 uo
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o 300 0N f5§
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-j
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o c() 100 100 200 200 300 300 400 400 500 500 600 700 800 BOO (SEC) TIME (SEC) Figure 8.18 Limiting SLO Recirculation Recirculation Line Break Lower Downcomer Lower Downcomer Liquid Mass Mass AREVA NP Inc.
Browns Ferry Units Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Extended Power Uprate Uprate Revision 0 LOCA Break Spectrum Analysis Break Spectrum Analysis Page 8-16 Page 8-16
~ BROWNS BROWNS FERRY 0.6 FT2/PD FT2 PD MID SF- SF -BA TT 102P 105F SLO EPU rr) vi V,)
VJ
<~g o
o~ 5 a 0~ T
~g ct:'"
we I () VJ000 08
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00 100 100 200 200 300 400 500 500 600 700 B00 800 TIME (SEC) (SEC) Reci rculation Line Break Figure 8.19 Limiting SLO Recirculation Break Intact Loop Discharge Discharge Lii Linene Liquid Mass Mass 0 0 0 FERRY 0.6 FT2/PD MID SF BROWNS FERRY BROWNS SF-BATT 102P/105F SLO EPU 0 0 ,
- =0 0
00 0 0 m -'0
~o vi!;j!
VJ 0
*r (11 08 Do 58 an 0"'
- 0
- Jo zo Wo
-,1<:
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- J~
00 100 200 300 400 300 00 100 200 TIME 400(SEC) TIME (SEC) 500 500 600 700 800 Figure 8.20 Limiting Limiting SLO Recirculation Recirculation Line Break Upper Plenum Liquid Mass Mass AREVA NP Inc.
Browns Ferry Units 1, 2, and and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Uprate Revision 0 LOCA Break Spectrum Analysis Spectrum Analysis Page 8-17 8-17 g BROWNS FERRY 0.6 FT2 PD MID SF -BA TT 102P 105F SLO EPU / g Q~- 0
-o
_j EL
-j 100 200 300 400 400 500 600 700 BOO (SEC)
TIME (SEC) Figure 8.21 Limiting SLO Recirculation Recirculation Line Break Break Lower Plenum Liquid Mass Mass I [
]I Figure 8.22 Limiting SLO Recirculation Recirculation Line Break Break Hot Channel Inlet Flow Rate Rate AREVA AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 Browns EMF-2950(NP) EMF-2950(NP) Uprate Extended Power Uprate Revision 0 Revision LOCA Break Spectrum Spectrum Analysis Analysis Page 8-18 8-18 [
]I Figure 8.23 Limiting Limiting SLO Recirculation Recirculation Line Break Break Hot Channel Channel Outlet Outlet Flow Rate
[ I] Figure 8.24 Limiting SLO Recirculation Recirculation Line Break Break Hot Channel Channel Coolant Temperature Temperature at the Limiting Node Node AREVA NP Inc.
Browns Browns Ferry Units Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Power Uprate Revision 0 Revision LOCA Break Spectrum Spectrum Analysis Analysis 8-19 Page 8-19 [I: I 1 Figure 8.25 Limiting SLO Recirculation Recirculation Line Break Break Channel Quality Hot Channel Quality at the Limiting Node Node (( 1I Figure 8.26 Limiting SLO Recirculation Recirculation Line Break Hot Channel Heat Heat Transfer Coef. at the Limiting Node Node AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 Browns EMF-2950(NP) EMF-2950(NP) Extended Power Power Uprate Uprate Revision Revision 0 LOCA Break Spectrum Spectrum Analysis Analysis Page 8-20 2500 o----a PCT Rod (Rod 11 ) 0----0 Water Channel I!r------i>. Fuel Channel 2000 2000
~
....:::JCl>
--+-' 1500 1500
....0 Cl>
0u a. E E I--Cl> I-
\
o0> 1000 c
'6 "0
C)0 U 500 0 o 50 100 150 150 200 250 300 350 400 Time (sec) Figure 8.27 Limiting SLO Recirculation Recirculation Line Break Cladding Temperatures Cladding Temperatures AREVA AREVA NP Inc.
Browns Ferry Units 1,1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Revision 0 Revision LOCA Break Spectrum Spectrum Analysis Page 9-1 9.0 Long-Term Coolability Long-Term Coolability Long-term Long-term coolability coolability addresses maintaining a water level addresses the issue of reflooding the core and maintaining adequate to cool the core and remove decay heat for an extended adequate extended time period following a non-recirculation line breaks, the core can be reflooded LOCA. For non-recirculation reflooded to the top of the active fuel and be adequately adequately cooled indefinitely. For recirculation recirculation line breaks, the core will initially remain remain provided by the water filling the jet pumps to aa covered following reflood due to the static head provided covered approximately two-thirds core height. Eventually, the heat flux in the core will not be level of approximately be adequate to maintain a two-phase adequate over the entire length of the core. Beyond this two-phase water level over this adequately cooled by core spray. time, the upper third of the core will remain wetted and adequately two-thirds core height with one core spray system operating is Maintaining water level at two-thirds Maintaining sufficient to maintain sufficient maintain long-term coolability demonstrated by the NSSS vendor coolability as demonstrated vendor (Reference (Reference 8). AREVA NP Inc.
Browns Ferry Units 1,1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Revision Revision 0 LOCA Break Spectrum Spectrum Analysis Page 10-1 10.0 Conclusions Conclusions The major major conclusions of this LOCA break spectrum analysis are:
- The limiting limiting recirculation line break is a 0.5 ft ft22 split break in the pump discharge discharge piping piping with single failure SF-BATT and a mid-peaked mid-peaked axial shape at 102% 102% EPU and 105%105%
rated core flow for two-loop operation.
- The limiting break analysis identified acceptance criteria specified in identified above satisfies all acceptance in 10 CFR 50.46. The analysis is performed performed in accordance accordance with 10 CFR 50.46 50.46 Appendix Appendix K requirements.
- Peak PCT < 2200°F2200'F (1998°F).
- Local cladding Local cladding oxiqation oxidation thickness < 0.17 (0.0183).
- Total hydrogen generation Total hydrogen generation < < 0.01 (the break spectrum spectrum analysis analysis had a maximum maximum planar average average MWR 0.01, it is concluded MWR of less than 0.01, concluded that core-wide core-wide metal-water reaction (CMWR)
(CMWR) would be less than 0.01). 0.01).
- Coolable geometry, Coolable geometry, satisfied by meeting meeting .peak peak PCT, local cladding cladding oxidation, oxidation, and total hydrogen generation criteria.
- Core long-term Core long-term cooling, satisfied satisfied by concluding core flooded flooded to top of active fuel or core flooded to the jet pump suction suction elevation elevation with one core spray operating.
- Breaks in the non-recirculation non-recirculation lines lines are less limiting limiting than the most severe severe break break in the the recirculation line.
recirculation
- The MAPLHGR MAPLHGR limit multiplier for SLO is 0.85 for ATRIUM-10 ATRIUM-1 0 fuel. This multiplier multiplier ensures that a LOCA from SLO is less limiting limiting than a LOCA from two-loop operation.
operation. The limiting limiting break characteristics characteristics determined determined in this report can be referenced referenced and used in future future Browns Ferry Units 1, 2, and 3 LOCA analyses to establish the MAPLHGR MAPLHGR limit versus versus exposure for ATRIUM-10 exposure ATRIUM-10 fuel. AREVA NP Inc.
Browns Ferry Units 1, 2, and 3 EMF-2950(NP) EMF-2950(NP) Extended Uprate Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis 11-1 Page 11-1 11.0 References References
- 1. EMF-2361 (P)(A) Revision Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome Evaluation Model, Framatome ANP, May 2001.
2001.
- 2. XN-CC-33(P)(A) Revision XN-CC-33(P)(A) Revision 1, HUXY: AA Generalized GeneralizedMultirod Heatup Code MultirodHeatup Code with 10 CFR CFR 50 Appendix K HeatupHeatup Option Option Users Manual, Exxon Nuclear Company, Users Manual, November 1975.
November
- 3. XN-NF-82-07(P)(A) Revision 1, Exxon Nuclear XN-NF-82-07(P)(A) Company ECCS Cladding Nuclear Company Cladding Swelling and Rupture Model, Rupture Model, Exxon Nuclear Company, November November 1982.
- 4. XN-NF-81-58(P)(A) Revision 2 and Supplements XN-NF-81-58(P)(A) Supplements 1 and 2, RODEX2 Fuel Fuel Rod Thermal-Thermal-Mechanical Response Mechanical Response Evaluation Evaluation Model, Model, Exxon Nuclear Nuclear Company, March 1984.
1984. EMF-2292(P)(A) Revision 0, ATRIUM TM-1O: Appendix Spray Heat Heat Transfer
- 5. EMF-2292(P)(A) ATRIUMTM-10: K Spray Coefficients, Coefficients, Siemens Power September 2000 Power Corporation, September 2000...
- 6. EMF-2925(P) Revision EMF-2925(P) Browns Ferry Revision 2, Browns Ferry Units 1, 1, 2, and 3 Extended Extended Power Uprate Plant Power Uprate Plant ParametersDocument, Parameters Document, Framatome Framatome ANP, December December 2003.
- 7. FerryNuclear Browns Ferry Nuclear Plant FSAR, Amendment Plant FSAR, Amendment 19.06, Tennessee Tennessee Valley Authority.
- 8. NEDO-20566A, Analytical Model for for Loss-of-Coolant Loss-of-CoolantAnalysis in Accordance with CFR Appendix K, 10 CFR K, General September 19.86.
General Electric Company, September AREVA NP Inc.
1, 2, and 3 Browns Ferry Units 1, EMF-2950(NP) EMF-2950(NP) Extended Power Uprate Extended Revision 0 LOCA Break LOCA Break Spectrum Spectrum Analysis Page A-1 A-1 Appendix Appendix A Supplemental Information Supplemental Information The tables and figures presented presented in this appendix appendix provide provide additional information requested requested by by TVA for review. The supplemental supplemental information provided provided is: Major computer computer codes used Table A1 Table A. 1 Supplemental limiting break data Supplemental Tables A. Tables A 2-A. 2-A 4, Figures A1-A3 Figures A. 1-A. 3 Limiting recirculation line pump discharge large break (DEG) (OEG) data data Tables A.5-A. Tables A5-A 7, 7, Figures A4-A33 Figures A.4-A.33 recirculation line pump suction large break (DEG) Limiting recirculation (OEG) data. Tables A.8-A. Tables A8-A10, 10, Figures Figures A.34-A.63 A34-A63 CLTP CL ft2 split break data TP 0.5 ft2 data Tables A11-A13, Tables A. 11-A. 13, Figures FiguresA64-A93 A.64-A.93 AREVA NP Inc.
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Browns Ferry Units Units 1, 2, and 3 Extended Power Uprate Extended Uprate EMF-2950(NP) EMF-2950(NP) Soectrum Analysis LOCA Break Spectrum Analysis Revision 0 Revision Distribution Distribution Controlled Distribution Controlled Distribution Richland DJ OJ Braun Braun ME ME Garrett CE CE Hendrix AB Meginnis Meginnis RR Schnepp Schnepp E-Mail Notification Notification DB McBurney OB McBurney MS Stricker Stricker SA Tylinski AREVA AREVA NP Inc.}}