ML19345E494
| ML19345E494 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 09/19/1977 |
| From: | Bixel D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Desiree Davis Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8102040679 | |
| Download: ML19345E494 (12) | |
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Se$ e=ber 19, 1977 0; Q sf Director of Nuclear Reactor Regulation Att: Mr Don K Davis, Acting Branch Chief Operating Reactor Branch No 2 US Nuclear Regulatory Co:=".ission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCX FOINT PLANT - VFn"IFICATION OF REDUNDANT CORE SPRAY FLOW RATES Transmitted attached is an evaluation of the adequacy of the redundant ecre spray system at Big Rock Point based upon actual bundle spray flows and bundle evaporation rates.
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L David A Bixel I
Nuclear Licensing Ad=inistrator CC: JGKeppler, USIRC 1.
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Attochment 1 i
I ADEQUACY OF REDUNDANT CORE SPRAY
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r An evaluation was made of the adequacy of the redundant core spray syste= based
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on measured spray flow data from Reference 1 and on maximum expected fuel bundle peakingfactorsduringCycle15 operation. The results of this evaluation show M
that the redundant core spray system provides adequate capability of decay heat removal following a LOCA over the entire range of break sizes up to and including the design basis accident (DBA) which assumes a double-ended guillotine break in a recirculation pump suction lin, The method of evaluation and conclusions ara discussed in more detail below.
Spray Flow Rates Spray flow rates to each of the Sk fuel bundles in the core vere determined based l
on test data for bottom only and top and bottom combined steam entry modes. Ves-sel pressures of 25, 50 and 75 psig were considered for each mode of steam entrf.
1 It should be noted that the bottom only steam entry mode is most cheracteristic of tne vessel conditions that would exist following the blevdown since the stes:
dru= vould e=pty quickly, nor= ally before rated spray, and the only water left to flash would be in the lover plenu=. Top only steam entry is considered i=pos-sible. Consu=ers Power Co and General Electric have reviewed the Big Rock Point Plant primary system geo=etrf and have deter =ined that no situation could exist following a LOCA in which there is top entrf stem without coincident botto:
entry steam.
In some instances, the test results indicated,that certain fuel bundle locations would receive significantly lower flow than the corresponding locations assuming octant core symmetry. However, the test report concluded that these lov flow areas were a result of test vessel effects and were not a function of the nos:le design.
Hence, where spray flow data for syn =etric bundle locations was avail-able, it was decided that it was most appropriate to average the available in-f{riationtodeter=inetheexpectedbundleflowtoagivenlocationin the corb This procedure is illustrated in Figure 1 which is a typical set of test data frc= Reference 1 shoving =easured flevs to each of the instrumented icaations.
Locations with si=ilar cress-hatching would be averaged in deter-
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=ining the expected bundle flows.
1
k Octant bundle flows as derived by the procedure described above are shown in Figures 2 and 3 for each of the test conditions.
Bundle Powers At]achcorelocetion,thehihestbundlepeakingfactoratanytimeduring 6
Cycle 15 was detemined. These bundle peaking factors are provided in Fihek.
Evaporation Rate The amount of water required to remove the bundle decay heat through evapora-tion (ie, the evaporation rate) was determined for each vessel pressure condi-tion. The calculation assumed saturated spray water, and the ANS decay heat fraction for infinite irradiation at the earliest time at which rated spray flow was assumed to occur in the O CS analysis (ie, 20.h seconds for the DBA).
The calculated evaporation rates in terms of bundle peaking factor (FR (assu=ing 220 IG reactor operation) are:
Vessel Pressure Evaeoration Rate 25 Psig 0 97 x F R
50 Psig 1.009 x F3 75 Psig 1.0h3 x FR Resulti Spray flow / evaporation rate ratios for each stea= entr/- mode at each of the_three vessel pressures were calculated f;r each core location using the information described above.
Figures 5 and 6 provide the results of thic calculation. The minimum spray flov/evaporttien rate ratios calculated for the two modes of steam entry are smme ized below:
Minimum Steen Entry Mcde Spray Flev/ Evaporation Rate Botton Only 1.70 Top and Bottc=
1.h3 Discussion Spgsy cooling tests (Reference 2) conducted for a 12-foot long, h9 rod, h IGg buhMewithsprayratesbetween2.0and05gpmhaveshownvirtuallynochange in'the =aximum clad te=perature transient for spray rates between 2.0 and 1.0 gpm (corresponding to spray flov/ evaporation rate ratios for the test initial condition cf 1.13 and 0 57, respectively), and only a slightly higher
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temperature for a spray rate of 0 5 gpm. Figure 21 from Reference 2 is attached to illustrate this fact.
It is expected that the same trends vould result for the BRP fuel assemblies.
f* should be noted that the peak fuel n.
bundle in Cycle 15 vill be operated at less than 3.6 MW ; and that the' minimum g
tegyflowforeitherbottomonlyortopandbottomcombinedsteamentrywas 1.88 gpm to a single bundle.
Based on these test results, it he.s been concluded that a minimum spray flow rate of '. 0 gpm vill provide adequate core cooling in the event of a LOCA.
References 1.
Big Rock Point Spray Test Report, 8/9/77 2.
" Core Spray and Core Flooding Heat Transfer Effectiveness in a Full-Scale Boiling Water Reactor Bundle," APED-5529, June 1968.
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I BIG ROCK FOINT COFE SFFAY TEST MULTIF1.E PO771r SFRAY TEST
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SB61-22"r-4 DATE 7/20/77 PfEE 2 OF 3
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@SSEL FfiESEURE (FSIG) 25, TEMPERATURE (IEG F) 271
' WATER FLOW (CFM) 42Or TEMF1ERATLFE (IEG F) 87 NOZZLE NO.
MULTI (AA)
(ESSEL GRID FEFRESENTATION (GFM) 50 X
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7.03 X
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X 5.55
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X 5.42 5.30 X
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X 7.31 X
X 5.61 3.61
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X 5.67 3.33 3.28 4.12 4
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Figure 1
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6.87 2.23 g-5.h2 5.30 3.85 6.07 4,
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46.61 3.61 6.12 3.39 3.h7 h.23 5.67 3.38 3.28 3.8h 2.77 2.07 5.68 3.27 h.8h 2 90 2.57 2.57 (a)25psig (d) 50 psig 4
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3.66 h.69 5.0h 3.39 2.81 2.20 i-d'
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2.51 2.18 2.28 I
(c) 75 psis
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Firure 2.
Stray Flow Rates (GP!') - Bottom Steam Tr.try
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2.73 3.79
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2.82 3.77 2.87 3.h8 2.50 2.12 3 96 3.67 2.56 2.79 2.29 2.06 (a)25psig (b) 50 psig o
2.52 3.72 5.71 3.21 3.17 3.5h h.09 2.37 2.20 L-b*
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2.05 2.19 2.11 (c) 75 psig
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Firure 3.
Erray Flev P.ates (GP!O - Toe and Better. Stea-Fntrr
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Firure h.' Cycle 15 Hichest Bundla Peakinr Factors
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Mk.27 2.82 5.01 2.h7 2.61
.$. 32 k.76 2.81 h.01
'3.09 2.21 2.h2 6.28 3.91 9.19 3.08 2.96 h.68 (a)25psig (b) 50 psig 2.23 2,68 h.26 2.59 3.h1 3.83 2.6h 2.17 C.50 1
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2.58 2.h2 h.01 (c) 75 psig Figure 5.
stray Flow /Fvatoration Pate - Ectton Stear. Enter
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2.12 3.08 2.hk 3.96
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(a) 25 psig (b) 50 psig 1.86 2.70 h.31 2.27 P.30 2.69 3.19 1.83 2.50
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2.10 2.h3 3.72 (c) 75 psig Firure 6.
Stray Flov/ Evaporation Pate - Top and Botton F'en.m Entry
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NRC DISTRIBUTION nR PART 50 DOCKET MATERI AL FROM: Consumers Power Co.
DATE OF OCCUMF NT 8
Mr. Don K. Davis 09/19/77 Jackson, Michigan 49201 David A. Bixel oATE RECEivEo 09/22/77 hTTun O NOTO RIZE D PROP tNPUT PORM NUMBER OF CCPIES RECEIVED
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" tPTIZN ENCLQSU RE g
Consists of an evaluation fo the
_ r,y adequacy of the redundant core spray system at Big Rock Point based upon actual bundle spray flows and budle evaporation rates...
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