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| Issue Date: 3/1/84 DONALD C.COOK UNIT 2 CYCLE 5-5X STEAM GENERATOR TUBE PLUGGING LIMITING BREAK LOCA/ECCS ANALYSIS Prepared by: es, raun, au Licensing 5 Safety Engineering aJ ice Approve:~/2~/zw W.V.Ka ser, Manager PWR Safety Analysis Concur: an er, Lea Engineer Reload Fuel Licensing Approve: 7 tout, anager Licensing Im Safety Engineering Concur: organ, anager P posals 5 Customer Services Engineering Approve: o er, anager Fuel Engineering
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| &Technical Services grf EON NUCLEAR COMPANY, In+.84030802ih 840302 PDR ADOCK 050003ih P PDR NUCLEAR REGULATORY COMMISSION DISCLAIMER IMPORTANT NOTICE REGARDING CONTENTS AND USE OF THIS DOCUMENT PLEASE READ CAREFULLY This technical report was derived through research and development programs sponsored by Exxon Nuclear Company, Inc.It is being sub.mitted by Exxon Nuclear to the USNRC as part of a technical contri-bution to facilitate safety analyses by licensees of the USNRC which utilize Exxon Nuclear-fabricated reload fuel or other technical sewices provided by Exxon Nuclear for liaht water power reactors and it is true and correct to the best of Exxon Nuclear's knowledge, information, and belief.The information contained herein may be used by the USNRC in its review of this report, and by licensees or applicants before the USNRC which are customers of Exxon Nuclear in their demonstration of compliance with the USNRC's regulations.
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| Nthout derogadng from the fotegoing, neither Exxon Nuclear nor any person acting nn its behalf: A.Makes any warranty, express or implied, with respect to the accuracy, completeness, or usefulness of the infor-mation contained in this document, or that the use of any information, apparatus, method, or process disclosed in this document will not infringe privately owned rights;or 8.Assumes any liabilities with respect to the use of, or for danages resulting from the use of, any information, ap.paratus, method, or process disclosed in this document.XN-NF.FOO, 766 XN-NF-84-21(NP)
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| TABLE OF CONTENTS Section Pa<ac
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| ==1.0 INTRODUCTION==
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| .......................................
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| 1 2.0 S UMMARY~~~~~o~~~~~~~~~~~~~~~~~~~~t~~~~~~~~~~~~~~~~~2 3.0 LIMITING BREAK LOCA ANALYSIS.......................
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| 4 3.1 LOCA ANALYSIS MODEL...........................
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| 4 3~2 RES ULTS~~~~~~~~~~~~~~~~~t~~~~o~~~~~~~~~~~~~~~~6 4.0 CONCLUS IONS~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~54
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| ==5.0 REFERENCES==
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| .........--........-.......
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| ~.......55 LIST OF TABLES Table~Pa e 2.1 3.1 3.2 3.3 D.C.Cook Unit 2 LOCA/ECCS Analysis Su+nary........Donald C.Cook Unit 2 System Input Parameters
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| ......1.0 DECLG Break Analysis Parameters
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| ................
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| D.C.Cook Unit 2 1.0 DECLG Break Event Times.......3.4 1.0 DECLG Break fuel Response Results for C ycle 5 e~~~~~~~~~~~o~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~10 XN-NF-84-21(NP)
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| LIST OF fIGURES F i<iure~Pa e 3.1 RELAP4/EN Blowdown System Nodalization for D.C.Cook Unit 2..............................
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| 11 3.2 Oowncomer Flow Rate During Blowdown Period, 1.0 DECLG Break...................................
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| 12 3.3 3.4 Upper Plenum Pressure during Blowdown Period, 1.0 OECLG Break...........................
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| 13 Average Core Inlet Flow during Blowdown Period, 1.0 DECLG Break...........................
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| 14 3.5 3.6 Average Core Outlet Flow during Blowdown Period, 1.0 OECLG Break...........................
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| 15 Total Break Flow during Blowdown Period, 1.0 DECLG Break...................................
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| 16 3.7 Break Flow Enthalpy during Blowdown, 1.0 OECLG Break...................................
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| 17 3.8 Flow from Intact Loop Accumulator during Blowdown Period, 1.0 DECLG Break..................
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| 18 3.9'3.10 Flow from Broken Loop Accumulator during Blowdown Period, 1.0 DECLG Break..................
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| 19 Pressurizer Surge Line Flow during Blowdown Period, 1.0 DECLG Break......................
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| ~....20 3.11 Heat Transfer Coefficient during Blowdown Period at PCT Node, 1.0 DECLG.Break, 2.0 MWO/kg Case...................................
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| 21 3.12 Clad Surface Temperature during Slowdown Period at PCT Node, 1.0 DECLG Break, 2.0 MWO/kg Case 22 3.13 Depth of Metal-Water Reaction during Slowdown Period at PCT Node, 1.0 OECLG Break, 2.0 NWD/kg Case...................
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| 23 iv XN-NF-84-21(NP)
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| LIST OF FIGURES (Cont.)~Fi ere~Pa e 3.14 3.15 3.16 3.17 3.18 3.19 3.20.3.21 3.22 3.23 3.24 3.25 Average Fuel Temperature during Blowdown Period at PCT Location, 1.0 OECLG Break, 2.0 MWO/kg Case..............................'......
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| Hot Assembly Inlet Flow during Blowdown Period, 1.0 OECLG Break, 2.0 MWD/kg Case...........
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| Hot Assembly Outlet Flow during Blowdown Period, 1.0 DECLG Break, 2.0 MWD/kg Case...........
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| Heat Transfer Coefficient during Blowdown Period at PCT Node, 1.0 DECLG Break, 10.0 MWD/kg Case...................................
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| Clad Surface Temperature during Blowdown Period at PCT Node, 1.0 OECLG Break, 10.0 MWD/kg Case...................................
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| Depth of Metal-Mater Reaction during Blowdown, Period at PCT Node, 1.0 DECLG Break, 10.0 MWO/kg Case.Average Fuel Temperature during Blowdown Period at PCT Location, 1.0 DECLG Break, 10.0 MWD/kg Case...................................
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| Hot Assembly Inlet Flow during Blowdown Period, 1.0 DECLG Break, 10.0 MWD/kg Case..................
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| Hot Assembly Outlet Flow during Blowdown Period, 1.0 OECLG Break, 10.0 MWD/kg Case..................
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| Heat Transfer Coefficient during Blowdown Period at PCT Node, 1.0 OECLG Break, 47.0 MWD/kg Case..............
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| 1 Clad Surface Temperature during Blowdown Period at PCT Node, 1.0 DECLG Break, 47.0 MWD/kg Case...................................
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| Depth of Metal-Water Reaction during Blowdown Period at PCT Node, 1.0 OECLG Break, 47.0 MWD/kg Case...............
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| 24 25 26 27 28 29 30 31 32 33 34 35 v XN-NF-84-21(NP)
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| LIST OF FIGURES (Cont.)F iciure~Pa e 3.26 3.27 3.28 3.29 3.30 3.31 3.32'.33 Average Fuel Temperature during Blowdown Period at PCT Location, 1.0 DECLG Break, 47.0 MWO/kg Case..................................
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| Hot Assembly Inlet Flow during Blowdown Period, 1.0 DECLG Break, 47.0 MWD/kg Case.................
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| Hot Assembly Outlet Flow during Blowdown Period, 1.0 DECLG Break, 47.0 MWD/kg Case.........Accumulator Flow during Refill and Ref lood Periods, Broken Loop, 1.0 OECLG Break.............
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| Accumulator Flow during Refill and Ref lood Periods, Intact Loop, 1.0 OECLG Break.............
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| HPSI 5 LPSI Flow during Refill and Ref lood Periods, Broken Loop, 1.0 DECLG Break.............
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| HPSI Im LPSI Flow during Refill and Ref lood Periods, Intact Loop, 1.0 DECLG Break.............
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| Containment Back Pressure, 1.0 OECLG Break........36 37 38 39 40 41 42 43 3.34 3.35 3.36 3.37 Normalized Power, 1.0 OECLG Break, 2.0 MWD/kg Case...................................
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| Normalized Power, 1.0 DECLG Break, 10.0 MWD/kg, Case..................................
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| Normalized Power, 1.0 OECLG Break, 47.0 MWD/kg Case..................................
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| Ref lood Core Mixture Level, 1.0 OECLG Break, 8 55 ENC Core......................................
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| 44 45 46 47 ,3.38 3.39 3.40 Ref lood Downcomer Mixture Level, 1.0 DECLG Break...................................
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| Ref lood Upper Plenum Pressure, 1.0 DECLG Break....Core Flooding Rate, 1.0 DECLG Break...............
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| 48 49 50 vi XN-NF-84-21','P
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| )LIST OF FIGURES (Cont.)~Fi ere 3.41 TOODEE2 Cladding Temperature versus Time, 1.0 DECLG Break, 2.0 MWD/kg Case..................
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| ~Pa e 51 3.42 3.43 TOODEE2 Cladding Temperature versus Time, 1.0 DECLG Break, 10.0 MWD/kg Case...............,..
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| 52 TOODEE2 Cladding Temperature versus Time, 1.0 DECLG Break, 47.0 MWD/kg Case.................
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| 53 XN-NF-84-21(NP)
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| ==1.0 INTRODUCTION==
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| Large break LOCA/ECCS analyses were performed in 1982(1 2)to support operation of the D.C.Cook Unit 2 reactor at 3425 MWt with ENC fuel.Reference 1 presented analytical results for a spectrum of postulated large break LOCAs.The limiting break was identified as the 1.0 DECLG break.Reference 2 presented results for the previously identified limiting break using the EXEM/PWR(3)
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| ECCS models, except GAPEX was used as the fuel performance model in place of RODEX2.The RODEX2 code was not approved by the NRC for use in ECCS analyses in 1982.The analysis therefore used the GAPEX(4)code which was approved by the NRC to calculate fuel properties at the initialization of the LOCA calculation.
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| The Reference 2 report documented the results of calculations with one and two LPSI pumps operating.
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| At equivalent core peaking limits, higher peak cladding temperatures (PCTs)were calculated in the LOCA analysis when two LPSI pumps were assumed operating.
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| The Reference 2 analysis with two LPSI pumps operating was performed for Cycle 4 operation of D.C.Cook Unit 2.This report documents the results of a LOCA/ECCS analysis to support operation of the D.C.Cook Unit 2 reactor for Cycle 5 at a thermal power rating of 3425 MWt, with up to 5X of the steam generator tubes plugged, with two LPSI pumps operating, and for ENC fuel exposed up to a peak rod average burnup of 47 MWD/kg.The calculations were performed using the EXEM/PWR LOCA/ECCS models, including fuel properties calculated at the start of the LOCA transient with ENC's generically approved RODEX2 code.'(5) iY XN-NF-84-21(NP) 2.0 SUHMARY LOCA/ECCS calculations were performed to determine core peaking limits which permit operation of the O.C.Cook Unit 2 reactor within guidelines specified by 10 CFR 50.46 and Appendix K.(6)The calculations assumed operation:
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| 1)At a thermal power of 3425 MWt;2)With 5X average steam generator tube plugging;and 3)With the Cycle 5 core configuration (85ÃENC fuel).The calculations were performed for the previously identified limiting break, the 1.0 OECLG break, with full ECCS flow.The results of the analysis are summarized in Table 2.1.The analysis supports operation of the O.C.Cook Unit 2 reactor for Cycle 5 at a total peak limit (FqT)of 2.04 and a corresponding F<H limit of 1.55.
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| XN-NF-84-21(NP)
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| Table 2.1 O.C.Cook Unit 2 LOCA/ECCS Analysis Suranary Results for the C cle 5 Core Confi uration (85K fNC Fuel Peak Rod Average Burnup (MMD/kg)FT Q FZH T Peak Cladding Temperature (oF)Maximum Local Zr-H20 Reaction (X)Total Zr-H20 Reaction 2.0 2.04 1.55 2176 7.4<1.0 10.0 2.04 l.55 2178 7.4<1.0 47.0 2.04 1.55 2129 6.5<1.0 XN-NF-84-21(NP) 3.0 LIMITING BREAK LOCA ANALYSIS This report supplements previous LOCA/ECCS analyses performed and documented for D.C.Cook Unit 2.A spectrum of LOCA breaks was performed and reported in XN-NF-82-35.(1)
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| The limiting LOCA break was determined to be the large double-ended guillotine break of the cold leg or reactor vessel inlet pipe with a discharge coefficient of 1.0 (1.0 DECLG).Reference 2 established that for D.C.Cook Unit 2 it is more limiting in the LOCA analysis to assume no failur'e of a LPSI pump;The analysis performed and reported herein considers:
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| 1)That 5X of the steam generator tubes are plugged;2)That 85K of the Cycle 5 core is composed of ENC fuel;3)That both LPSI pumps are operational; and 4)That ENC fuel may be exposed to a peak average burnup of 47 MWD/kg.3.1-LOCA ANALYSIS MODEL The Exxon Nucleal Company EXEM/PWR-ECCS evaluation model was used to perform the analyses required..
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| This model(3)consists of the following computer codes: RODEX2(5)code for initial stored energy;RELAP4-EM'(")
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| for the system blowdown and hot channel blowdown calculations; ICECON'(8) for the computation of the ice condenser containment backpressure; REFLEX(3 g)for computation of system ref lood;and TOODEE2(3~1O~11) for the calculation of final fuel rod heatup.The Donald C.Cook Unit 2 nuclear power plant is a 4 loop Westinghouse pressurized water reactor with ice condenser containment.
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| The reactor coolant system is nodalized into control volumes representing 1 reasonably homogeneous regions, interconnected by flow-paths or"junctions".
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| XN-NF-84-21(NP)reasonably homogeneous regions, interconnected by flow-paths or"junctions".
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| The system nodalization is depicted in Figure 3.1.The unbroken loops were assumed symmetrical and modeled as one intact loop with appropriately scaled input.Pump performance curves characteristic of a Westinghouse series 93A pump were used in the analysis.The transient behavior was determined from the governing conservation equations for mass, energy, and momentum.Energy transport, flow r ates, and heat transfer were determined from appropriate correlations.
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| The Cycle 4 LOCA analysis(2) assumed that 15 of the steam generator tubes were, plugged.In the current analysis, the plant was modeled assuming asymmetric steam generator tube plugging: 3.33K of the tubes plugged in the intact loops, and 10.05 of the tubes plugged in the broken loop.The larger plugging in the broken loop results in higher PCTs.The primary coolant flow at full power was reduced by 1.1X from the current measured flow at the plant to account for the assumed average 5X steam generator plugging.Additionally, the core model assumed that the core is 85K ENC fuel, whereas the previous analysis assumed the Cycle 4 core configuration.
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| ENC fuel has a smaller rod diameter than the Westinghouse fuel it replaces.To offset the impact of increased flow area on the LOCA analysis results, the core power was reduced from 3425 NWt to 3411 MWt.System input parameters are given in Table 3.1.The reactor core is modeled with heat generation rates determined from reactor kinetics equations with reactivity feedback and with decay heating as required by Appendix K of 10 CFR 50.Chopped cosine axial power XN-NF-84-21(NP'rofiles are assumed with the maximum axial peaking factor used in the analysis given in Table 3.2.The analysis of the loss-of-coolant accident is performed at 102 percent of rated power.The core power and other parameters used in the analyses are given in Table 3.1.3.2 RESULTS Table 3.3 presents the timing and sequence of events as determined for the large break guillotine configuration with a discharge coefficient of 1.0 for full ECCS operation.
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| Table 3.4 presents the results of the exposure analysis for Cycle 5 composed of 85K ENC fuel.Results of the analyses are given in Figures 3.2 to 3.43.Figures 3.2 to 3.10 provide plots of key system blowdown parameters versus times.Figures 3.11 to 3.28 provide plots of key core responses during the blowdown period.Figures 3.29 to 3.32 provide the ECCS flows in the broken and intact loop during the refill period.F igure 3.33 presents the containment pressure during the LOCA.Figures 3.34 to 3.36 present the normalized power during the LOCA for the three exposure cases analyzed., Figures 3.37 to 3.40 provide results from the reflood portion of the transient for the case in which 855 of the core is ENC fuel.Finally, Figures 3.41 to 3.43 provide the response of the fuel during the refill and reflood periods of the LOCA transient for the fuel burnup cases investigated.
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| XN-NF-84-21 (NP)Table 3.1 Donald C.Cook Unit 2 System Input Parameters Thermal Power, MWt*Core, MWt Pump, MWt Primary Coolant Flow, Mlbm/hr Primary Coolant Volume, ft3 Operating Pressure, psia Inlet Coolant Temperature, oF Reactor Vessel Volume, ft3 Pressurizer Volume, Total, ft3 Pressurizer Volume, Liquid, ft3 Accumulator Volume, Total, ft3 (each of four)Accumulator Volume, Liquid, ft3 (each of four)Accumulator Pressure, psia Steam Generator Heat Transfer Area, ft2-SG1, SG2, SG3, SG4 Steam Generator Secondary Flow, ibm/hr-SG1, SG2,, SG3, SG4 Steam Generator Secondary Pressure, psia Reactor Coolant Pump Head, ft Reactor Coolant Pump Speed, rpm Moment of Inertia, ibm-ft2 Cold Leg Pipe, I.D.in.Hot Leg Pipe, I.D.in.Pump Suction Pipe,.I.D.in.Fuel Assembly Rod Diameter, in.Fuel Assembly Rod Pitch, in.Fuel Assembly Pitch, in.Fueled (Core)Height, in.Fuel Heat Transfer Area, ft2**Fuel Total Flow Area, Bare Rod, ft2**Refueling Water Storage Tank Temperature, oF Accumulator Water Temperature, oF*Primary Heat Output used in RELAP4-EM Model=**ENC Fuel Parameters.
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| 1.02 x 3425=3425 3411 14 143.1 11,768 2250 542 4945 1800 1080 1350 950 636 11,588, 3(12,446)3.505 x 106 3(3.764 x 106)799 277 1189 82,000 27.5 29.0 31.0 0.360 0.496 8.466 144.0 57,327 53.703 80 120 3493.5 MWt XN-'NF-84-21 (NP ,'able 3.2 1.0 DECLG Break Analysis Parameters Peak Rod Average Burnup (MWD/kg)Total Core Power (MWt)*Total Peaking (F~)T Fraction Energy Deposited in Fuel Fully Moderated Core~Voided Core 2.0 3411 2.04 0.974 0.954 3411 2.04 0.974 0.954 47.0 3411 2.04 0.974 0.954 C cl e 5 (85K ENC Fuel)Peak ing~Axial x Engineering
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| .Enthalpy Rise (F~H)T 1.316 1.55 1.316 1.55 1.316 1.55*2K power uncertainty is added to th,is value in the LOCA analysis; XN-NF-84-21 (NP,'able 3.3 D.C.Cook Unit 2 1.0 DECLG Break Event-Times Event Time (sec.)Start Break Initiation Safety Injection Signal Accumulator Injection Broken Loop Intact Loop End of Bypass Safety Pump Injection Start of Ref lood Accumulator Empty Broken Loop Intact Loop 0.00 0.05 0.65 3.2 15.5 24.31 25.65 40.48 44.2 52.9 10 XN-NF-84-21(NP
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| )Table 3.4 1.0 DECLG Break Fuel Response Results for Cycle 5 Peak Rod Average Burnup (MWD/kg)Initial Peak Fuel Average Temperature (oF)Hot Rod Burst~Time (sec)~Elevation (ft)~Channel Blockage Fraction Peak Clad Temperature
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| ~Time (sec)'levation (ft)~Temperature (oF)Zr-Steam Reaction Local Maximum Elevation (ft)~Local Maximum (X)*~Core Maximum 2.0 2151 62.3 6.75.24 295 9.38 2176 9.38 7.4<1.0 10.0 2060 63.7 7.00.27 296 9.38 2178 9.38 7.4<1.0 47.0 1629 70.1 7.50.47 297 9.38 2129 9.38 6.5<1.0*Values 400 sec into'LOCA transient.
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| STf AH Gf:,ERATOR PRESSURI?ER STEAK GENE RATOR Q4S 60 59 QO 39 QS INTACT LOOP Q HOOEL VOLIRIE Q reer UNCTION REAC'IOR VESSEL Qi BROKE N LOOP BREAK LOCATION 18 18 19 Q46 19 20 20 21 56 55 Q9 Q 3 HOT LfG g?O>>PTIHP QI 13 13 I 14@47 41@48 X32 LI9j Q37 44 Q3 38 34 40 Sz 26 26 los g HI Q47 43 15 HOT LEG QO QS Qi PllHP 74 16 16 Q?I??22 10 Q47 29 COKTA IIOIENT~6~3~33 3?33 Q35 4?g3 40 36 I 31 30 3 Q44 23 ACCIRRILATOR ACCIARILATOR Figure 3.1 RELAP4/EN Blowdown System Nodalization for D.C.Cook Unit 2 Cs Cl 1~0 DC COOK 2 17)(17~DECL BONo 5 X AVEe PLUG~10<i 3+3~3~~PLUGt lYl m X 4-Q 1t ic 2A R4 TXHE'FTER BRE'AK (SE'C 3 Figure 3.2 Oowncomer Flow Rate Ouring Blowdown Period, 1.0 OECLG Break I T7 I CO I PO 1.0 DC COOK 2 17X17,DECL BDN, 5X AVE.PLUG,10K 3+3'3X PLUG, pl$0 bl 4J.K CL D it Q 5l 2i TINE AFTER BREAK (SEC)Figure 3.3 Upper Plenum Pressure During Blowdown Period, 1.0 DECLG Break
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| ~D to tA Ky 4l ho Kg~a Ct 4.W LL C)Qe 1.0 DC COOK R 17X17.0ECL BDN, 5i!AYE.PLUG,101 3+3.3X PLUG, CKg l 12.M z,a?i TIHE AFTER BREAK (SEC)Figure 3.4 Average Core Inlet Flow during Blowdown Period, 1.0 OECLG Break 1 0 DC COOK 2 17X17~OECL 80hli 5X AVE PLUGr 10K 3+3 3X PLUGS hl Vl K gg O--jo 8 t-y O 4Jy D<a C9 CK 1K iC t0 R4 TIHE AFTER BREAK (SEC)Figure 3.5 Average Core Outlet Flow during Blowdown Period, 1.0 OECLG Break 1.0 DC COOK 2 17 X17.DECL B DH.5 X AVE PLUG.10 X 3+3~3 X PLUG.lxi f hD O Dg 4-o R-)8 Q et lt RO 2i TIHE AFTER BREAK (SEC)3t, Figure 3.6 Total Break Flow during Blowdown Period, 1.0 DECLG Break 1 0 OC COOK R 1" 0 OECLG BON m8%5 ul g Yessel Side~Pump Side TXHE'SE'C)Figure 3.7 Break Flow Enthalpy During Blowdown, 1.0 DECLG Break OC I n I CO I Po>~8 K K K 3c Oo Qo g D 1 0 OC COOK 2 17X17~OECL BOH, 5X AVE'.PLUG.10Ã3+3~3X PLUG P-8 CK Q Bg~~9 lt ll Sl th TIME AFTER BREAK (SEC)Figure 3.8 Flow from Intact Loop Accumulator during Blowdown Period, 1.0 OECLG Break O hfdf lA>>~e4 K K K 3c Og d~Z, 1 0 DC COOK 2, 17X17~DECL BDNr 5 X AVE PLUG>10 X 343 3 X PLUGS K O l-a CEQ X;Og K lR I t0 Rl TIME AFTER BREAK (SEC).32 Figure 3.9 flow from Broken Loop Accumulator during Blowdown Period, 1.0 OECLG Break lJ Qo mS wQ K hler D K bl z,~R 1 0 OC COOK 2 17X17 i DECL.Boer 5 X AVE PLUGS 10 X 343 3 X PLUGS Ko gi lK Vl tA hl Ko CL 1t I 2.0 Rl TAHE AFTER BREAK (SEC)Figure 3.10 Pressurizer Surge Line Flow during Blowdown Period, 1.0 OECLG Break OC I'l I CO I a 1.0 OC COOK 2 1~0 OCCLC ao t4 TETE t SEc)Figure 3.11 Heat Transfer Coefficient during Blowdown Period at PCT Node, 1.0 DECLG Break, 2.0 MWD/kg Case fi 1 0 OC COOk 2 1~0 OECLG FO RI TIHE (SEC)Figure 3.12 Clad Surface Temperature during Blowdown Period at PCT Node, 1.0 DECLG Break, 2.0 HWD/kg Case Qo~I H Lalm 5 gO LI gO L,~O CV RI 1.0 OC CQQl(R 1 0 OECLC RO.t4 TIRE'SEC)Figure 3.13 Depth of Metal-Water Reaction during Blowdown Period at PCT Node, 1.0 DECLG Break, 2.0 MWD/kg Case~'
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| CD AJ I 0)3 rl 1.0 OC COOK R 1.0 OECLt>C I n I CO I Figure 3.14 l lL N tD t4 Cl TAHE (SEC)Average Fuel Temperature during Blowdown Period at PCT Location, 1.0 DECLG Break, 2.0 HWD/kg Case
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| ~%V~~~VVI~kJrV4(l.0 DC COOK Z.l D OECLG Figure 3.15 lR 1$EO LI tl 3t TIHE l SEC)Ilot Assembly Inlet Flow during Blowdown Period, 1.0 DECLG Break, 2.0 NWD/kg Case l 0 OC COOK 2.1.0 DECLG a0 U TIVE (SEC)Figure 3.16 Hot Assembly Outlet Flow during Blowdown Period, 1.0 OECLG Break, 2.0 HHD/kg Case i.o OC CCOK a.1..0 OECL&1S 8)Zi TINE (SE'C)Figure 3.17 Heat Transfer Coeffir.ient during Blowdown Period at PCT Node, 1.0 DECLG Break, 10.0 NWD/kq Case 1.0 DC COOK 2.1 0 DECLG 2,0 tl TXHE (SE'C)Figure 3.18 Clad Surface Temperature during Blowdown Period at PCT Node, 1.0 DECLG Break, 10.0 NWD/kg Case io>C I Tl I CO I a
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| ~I<y~~~lJ'Jl~l Jl Vl I V'I CD nJ K Cl Qe H X Oo H SI Cf LLJ CX i8<o H 1 0 OC COOK Z 1.0 OE'CLG hg Clg CD O al ll RO TINE'SEC)Figure 3.19 Depth of Metal-Water Reaction during Blowdown Period at PCT Node, 1.0 OECLG Break, 10.0 MWD/kg Case~4'~(0 OC I I CO I U 1.0 OC COOK 2 1 0 OE'CLG I KO tl 3Z, TIHE'SEC)Figure 3.20 Average Fuel Temperature during Blowdown Period at PCT Location, 1.0 DECLG Break, 10.0 NWD/kg Case io OC I n I CO I PO 1 0 DC COOK 2 1 0 DECLG i I lZ 1C tO ti t TIHE (SEC)Figure 3.?1 Hot Assembly Inlet Flow during Blowdown Period, 1.0 DECLG Break, 10.0 HND/kg Case (0 OC I ll I CO I a 1.0 DC COOK R 1.0 OE'CLG Figure 3.22 LK lQ.RO R,i Zl TINE'SEC)Hot Assembly Outlet Flow during Blowdown Period, 1.0 DECLG Break, 10.0 NWD/kg Case 1-0 OC COOK 2 1 0 OfCLi Figure 3.23 R R t0 t4 2S TINE t SE'C)Heat Tansfer Coefficient during Blowdown Period at PCT Node, 1.0 DECLG Break, 47.0 NWD/kg Case M 1.0 DC COOK 2 1 0 DECLG Figure 3.24 it 1S C4 U TXHE (SEC)Clad Surface Temperature during Blowdown Period at PCT Node, 1.0 OECLG Break, 47.0 HWO/kg Case 40>C I ll I CO I O 1 0 OC COOk 2 1 0 OECLP 4 1k N RO H t0 SR lS TAHE f SEC)Figure 3.25 Depth of Metal-Mater Reaction During Blowdown Period at PCT Node, 1.0 DECLG Break, 47.0 HWD/kg Case 40>C I ll I CO I o 1 0 OC COOK 2 1.0 OE'CLG Figure 3.26 lt LC tD U tl'n TEIDE (SEC)Average Fuel Temperature during Blowdown Period at PCT Location, 1.0 DECLG Break, 47.0 MND/kg Case 1 0 GC COOK 2 1 O.DECLG EO t4 TXHE (SEC)Figure 3.27 Hot Assembly Inlet Flow during Blowdown Period, 1.0 DECLG Break, 47.0 NWD/kg Case 3.-0 OC COOK K 1.0 OE'CLG figure 3.28 12 1f RO Z<tl TXvE (SEC)Hot Assembly Outlet Flow during Blowdown Period, 1.0 OECLG Break, 47.0 NWD/kg Case 8 CJI 1$t0 tl tl TIHE RFTER EOB'f t SEC)Figure 3.29 Accumulator flow during Refill and Ref lood Periods, Broken Loop, 1.0 DECLG Break 1k 1S t0 tl TIHE AFTER EOBY (SEC)Figure 3.30 Accumulator Flow during Refill and Ref lood Periods, Intact Loop, 1.0 OECLG Break U M 300 fQ 250 O 200 150 C4.P O O R O IX 100 50 0 0 50 100 150 200 250 300 TIME, (SEC)AFTER END-OF-BYPASS Figure 3.3l HPSI 8 LPSI Flow during Refill and Ref lood Periods, Broken Loop, 1.0 OECLG Break 350 C V)fQ O 1000 800 600 400 P O O O 200 0 0 300 50 100 150 200 250 TIME, (SEC)AFTER END-OF-BYPASS Figure 3.32 HPSI 8 LPSI Flow during Refill and Ref lood Periods, Intact Loop, 1-.0 DECLG Break 350 U)C4 P R z O O 22 21 20 19 18 1?16 15 0 50 100 150 200 250 TIME AFTER EOBY (SEC)figure 3.33 Containment Back Pressure, 1.0 DECLG Break 300 a50 1SO ZOO UO TINE t SECONDS)Figure 3.34 Nornali"ed Power,'.0 OFCLG Break, E.O NWD/kg Case
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| >C I rl I CO I Ql i0 SO lCO 2,00 2I0 TIME (SECONDS)ZOO'3CO 400 Figure 3.35 Normal ized Power, 1.0 OECLG Break, 10.0 HWD/kg Case pl CS X MO R,lO l0-LEO 1CO ZOO Z(0 TIME'SE'CONDS)Figure 3.36 Normalized Power, 1.0 DECLG Break, 47.0 MWD/kg Case'3CO<00 DCCP REFLOODo 1 0 DECLC FULL'CCS FLOW FQ=R 0$1 55 3525 MWT 10 SO 120 160 200 2(0 280 TIME FROM 80CREC (SEC)32C 360 ioo Figure 3.37 Ref lood Core Mixture Level, 1.0 DECLG Break DCC2 REFLOODo1 0 DECLG FULL ECCS FLOW FQ=2.04 1.55 3525 MWT<0$0 160 200 2(0 2$0 TIME FROM BOCREC (SEC)360 ioo Figure 3.38 Ref lood Oowncomer Mixture Level, 1.0 DECLG Break LU I I LIJ Ul'4 C Jl VC/0't OCC2.REFLOOD, 1.0 OECLG FULL ECCS FLOW FQ=?.04 1,55 3hR5 MWT 40 eo eo zoo zoo ceo TIME FROM BOCREC (SEC)3RO 360 400 Figure 3.39 Ref lood Upper Plenum Pressure, 1.0 DECLG Break e~
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| OCC2 REFLOOOr 1 0 OECLG FULL ECCS FLOW FQ 2, 0 I-1 55 3 5 25 HWT.C3 ILI~(A N z, H O O Q c4 Jw 4.LU CO O 40 160 200 240 280 TINE FROM BOCREC (SEC)Figure 3.40.Core Flooding Rate, 1.0 DECLG Break 320 380 400 oJ 1.PCT NOOE (NODE RL AT$.3t FT 1 RUPTLJRE'O NOOE (HODE'0 AT C.1$FT.)(0.0 40.0 120+0 1@0.0 2Ã.0 f40.0 Rl0.4 TX~E-SECaNOs 3'3C0.0<OKO Figure 3.41 TOODEE2 Cladding Temperature versus Time, 1.0 DECLG Break, 2.0 NWD/kg Case C:
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| F9~2.Oi FOH~1.55.2-22-85 RFL 1 PCT NODE (NOOE RL AT 3-31 FT)R.RUPTUREO HOOE t NODE 11 AT 7.00 FT l 40.0 l0.0 120 0 lCO 0 810.0 240.0 TINE-SECONDS tlo.o 3R9.0 3C0.0 lOKQ Figure 3.42 TOODEE2 Cladding Temperature versus Time, 1.0 DECLG Break, 10.0 NWD/kg Case F9~2 OkoFOH~1.55'G3 1.55 RF 1.PCT NOOK (NODE R1 AT 031 FT.)R.RUPTURED NODE l NODE 13 AT t.SO FT-)Ia I C5 K H l3~8~e4~~.0<0(0 380.0<0.0 00 0 3R0.0 120 0 1R0 0 R00.0 U0.0 Rl0 0 TXHE-SECONDS Figure 3.43 TOODEE2 Cladding Temperature versus Time, 1.0 DECLG Break, 47.0 HWD/kg Case 54 XN-NF-84-21(NP)
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| ==4.0 CONCLUSION==
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| S For breaks up to and including the double-ended severance of a.reactor coolant pipe, the Donald C.Cook Unit 2 Emergency Core Cooling System will meet the Acceptance Criteria as presented in 10 CFR 50.46 for operation with ENC 17x17 fuel operating in accordance with the LHGR limits noted in Table 2.1.That is: 1.The calculated peak fuel element clad temperature does not exceed the 2200oF limit.2.The amount of fuel element cladding that reacts chemically with water or steam does not exceed 1 percent of the total amount of zircaloy in the reactor.3.The cladding temperature transient is terminated at a time when the core geometry is still amenable to cooling.The hot fuel rod cladding oxidation limits of 175 are not exceeded during or after quenching.
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| 4.The core temperature is reduced and decay heat is removed for an extended period of time, as required by the long-lived r adio-activity remaining in the core.
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| 55 XN-NF-84-21(NP)
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| ==5.0 REFERENCES==
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| XN-NF-82-35,"Donald C.Cook Unit 2 LOCA ECCS Analysis Using EXEM/PWR Large Break Results," Exxon Nuclear Company, Inc., Rich-land, WA 99352, April 1982.(2)(3)(4), (5)(6)(7)(8)(9)(10)XN-NF-82-35, Supplement 1,"Donald C.Cook Unit 2 Cycle 4 Limiting Break LOCA-ECCS Analysis Using EXEM/PWR," Exxon Nuclear Company, Inc., Richland, WA 99352, November 1982.XN-NF-82-20(P), Rev.1, August 1982;Supplement 1, March 1982;and Supplement 2, March 1982,"Exxon Nuclear Company Evaluation Model EXEM/PWR ECCS Model Updates," Exxon Nuclear Company, Inc., Rich-land, WA 99352.XN-73-25,"GAPEXX: A Computer Program for Predicting Pellet-to-Cladding Heat Transfer Coefficients," Exxon Nuclear Company, Inc., Richland, WA, August 13, 1973.XN-NF-81-58(P), Rev.2,"RODEX2: Fuel Rod Thermal-Mechanical Re-sponse Evaluation Model," Exxon Nuclear Company, Inc., Richland, WA 99352, February 1983."Acceptance Criteria for Emergency Core Cooling Systems for Light Water Cooled Nuclear Power Reactors," 10 CFR 50.46 and Appendix K of 10 CFR 50.U.S.Nuclear Regulatory Commission letter, T.A.Ippolito (NRC)to W.S.Nechodom (ENC),"SER for ENC RELAP4-EM Update," March 1979.XN-CC-39, Rev.1,"ICECON: A Computer Program Used to Calculate Containment Backpressure for LOCA Analysis (Including Ice Condenser Plants)," Exxon Nuclear Company, Inc., Richland, WA 99352, November 1977.XN-NF-78-30(A),"Exxon Nuclear Company WREM-Based Generic PWR ECCS Evaluation Model Update ENC WREM-IIA," Exxon Nuclear Company, Inc., Richland, WA 99352, May 1979.XN-NF-82-07(A), Rev.1,"Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon Nuclear Company, Inc., Richland, WA 99352, March 1982.G.N.Lauben, NRC Report NUREG-75/057,"TOODEE2: A Two-Dimensional E~A 1 i," 1 5.
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| 56 XN-NF-84-21(NP)
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| (12)D.C.Cook Unit 2 Technical Specification, Appendix"A" to License No.DPR-74, Amendment No.48.(13)XN-NF-82-32(P), Revision 2,"Plant Transient Analysis for the Donald C.Cook Unit 2 Reactor at 3425 NWt: Operation with 5X Steam Generator Tube Plugging," Exxon Nuclear Company, Inc., Richland, WA 99352, February 1984.
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| XN-NF-84-21(NP)Issue Date: 3/1/84 DONALD C.COOK UNIT 2 CYCLE 5 5X STEAM GENERATOR TUBE PLUGGING LIMITING BREAK LOCA/ECCS ANALYSIS Distribution M.J.Ades D.J.Braun J.C.Chandler R.A.Copeland N.F.Fausz S.E.Jensen W.V.Kayser J.E.Krajicek G.F.Owsley H.G.Shaw G.A.Sofer R.B.Stout T.Tahvili AEP/H.G.Shaw (10)Document Control (5)}}
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