ML17229A864
| ML17229A864 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 02/14/1997 |
| From: | Blohm T, Chan K, Peterson R SARGENT & LUNDY, INC. |
| To: | |
| Shared Package | |
| ML17229A863 | List: |
| References | |
| MECH-0088, MECH-0088-R00, MECH-88, MECH-88-R, NUDOCS 9809230152 | |
| Download: ML17229A864 (38) | |
Text
IC>
Sargent; B Lvndy"'
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
Ger gene & l uncly CALcULATroNAxALYszs Fr oaroA PowER ST. LUczs STATzoN Urm 2 FOR
~ LIGHT (FPL)
TRANSIKNT TKNlPKIKATURKOF SPKNT FUKL POOL FOLLOMIN&FULL CORK OFFLOAD CALc. No.: MacH-0088 DATE: FEBRUARY 14, 1997 Rsvlsiow: 0 STATUS: SAFE'TY-RELATED PRoJEcT No.: 08477-016
~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ 0 0 ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
qso9ssosss vsovxs 05000389 V
PDR ADOCK P PDRQ
.S Gale No. MECH-0088 Revision: 0 Page: 1 Safety Related: Yes.
/7 Prepared by Reviewed by T. J. Blohm K Chan /
r CJl~ v
'Date Date
~It~ I 2.~! 7 Approved by J Peers ~Date Transient Temperature of Spent Fuel Pool Following Full Core ONoad Prepared by Sargent 8 Lundy for Florida Power and Light (FPL)
St. Lucie Station - Unit 2 Project No. 08477-016
4)
}~
'e.
'f For Transtcnt Temperature of Spent Fuel Pool Fol .'ull Core Cate. No. ~tfCH&tgg r -
~
SARGENT LUNDY Oflload Rcv. 0 ENGINEERS X Safety.Related Von-Safety-Related Pace Client Flotidd Pointer and Light Prepared by Date Project St. Lucie Unit 2 Reviewed by Date Proj. Vo. 084774l6 Equip. Vo.V/A Approved by Date System Code Subsystem Division File Vo.
~ection TABLE OF CONVENT
1.0 Purpose and Scope
2.0 Design Input 3.0 Assumptions 4.0 Approach 5.0 Calculations 14 6.0 Results 19 7.0 References 20 8.0 Appendices A. Computer Output for Case 1 i-35 B. Computer Output for Case 2 i-35 C. Computer Output for Case 3 I-33 D. Computer Output for Case 4 i-35 E. Computer Output for Case 5 i-35 F. Graphs 1-8 G. . Computer Output for Full Core Decay Heat Benchmark i-29 H. . Computer Output for Partial Core Decay Heat'Benchmark i-29
Calc. For Transient Tetnperature of Spent Fuel Pool F 8 l ull Core Late. No. ~tbClW$ 88 S.tttRGENT.- i UNDY, OtTload Rev. 0 ENGJNEERS Safety-Related .'ion-safety.Related pa-c a or Cliont Florida Po>>cr and Light Prepared by Date Project St. Lucie Unit 2 Rcvie>>ed by Date Proj. Yo. 084774)6 Equip. pro.lqlA Approved by Date System Code Subsystem Division File Xo.
1.0 PURPO E AND C P The purpose of this calculation is to determine the transient spent fuel pool temperature folloWing a fuel oNoad for the cases detailed below. The analysis is based on the total spent fuel pool heat load for full core oNoad given in Reference 1, which corresponds to the Cycle 10 refueling outage (Reference 12).
Case Time after reactor shutdown for 168 168 168 168 168 initiation of defueling, hours Offload quantity full core, full core partial full core full core core Initial spent fuel pool 106 106 106 106 106 temperature, F SFP heat excharlger shell side 100 100 100 100 95 (CCW) inlet temperature,'F Number of SFP l'umps SFP Pump Flow (gpm) 3000 1500 1500 1500 1755 CCW Flow (gpm) 3560 -3560 3560 3560 3560 N/A'IA Heat Exchanger Effectiveness 0.488 0.694 0.694 0.75 0.709 Special conditions NIA N/A Special conditions:
- 1. Stop fuel offload so that peak pool temperature does not exceed 140'F.
2.1 Spent Fuel Pool Heat Exchanger Parameters (Reference 11)
Case 2.
SFP Pump Flow (gpm) 3000,
'500 1500 1500 1755 CCW Flow (gpm) 3560 3560 3560 3560 3560 Heat Exchanger Effectiveness 0.488 0.694 0.694 0.75 0.709
0 al<<For Transient TcmpcmtutcofSpcm Fuel Poet F mc Full Cv Cale.,'vo. XtECtWh188 ARGENT - LUNDY P/flood Rev. 0 ENGINEERS X Safety-Related .'v'on-Sa fcn. Related Pase 4 of Client Ffottdu Povvcr and Ltaht Prepared by Date Project St. Lucic Unit 3 Reviewed b'v Date Proj. >o. 084'174l6 Equip YoN/A Approved by Date Svstern Code Subsystem Division File Xo.
2.2 Spent Fuel Pool Data (Reference 1) surface area 1194 ft gross volume 45,9S9 ft'.3 Heat Loads (Reference 1) 2.3.1 Prevjously Djscharged Fuel Heat Load:
Q = 2.37 x 10'TU/hr 2.3.2 Full Core Heat Load:
Time After Decay Time After Decay Shutdown Heat Load Shutdown Heat Load Hours x 10'TU/hr Hours x 10'TU/hr 100 210 25.04 105 33.68 220 24.58 110 32.99 230 24.16 115 32.35 240 23.76 120 31.75 250 23.39 125 31.18 260 23.03 130 30.65 270 22.70 135 30.14 280 22.39 140 29.67 290 22.09 145 29.22 300 21.80 150 28.79 310 21.53 155 28.39 320 21.26 160 28.01 330 21.01 165 27.65 . 340 20.77 170 27.30 '350 20.53 175 26.9'7 360 20.30 180 26.66 370 20.08 190 26.07 380 19.87 200 25.53 390 19.66
UM 4 J
'ale. For Transtent Temperature of Spem <<el Pool Fol' Full Core Cate. No. MKHits>SS SARGENT '. LUNDY Pflload Rev. 0 ENGINEERS X Safety-Related Son-Safety-Related Pane 6 of Client Florida Potter and Light Prepared by Date Project St. Lueie Unit Revietved by Date 08477-0l6 'roj..'fo.
Equip. fo.N/A Approved by Date System Code Subsystem Division File No.
2.4 Non-Water Materials In Pool (ReferhRcep ~-
2.4.1 Fuel Assemblies (Reference 1)
Spent Fuel Core 'otal Weight of Zircaloy (Ibm) 174,509 61,791 236.300 Weight of Stainless Steel (Ibm) 34,747 12,007 46,754 Weight of UO, (Ibm) 612,231 213,042 825.273 2.4.2 Fuel Racks (Reference 1) material stainless steel volume 1952.53 ft 2.4.3 Liner (Reference 1) material type 304 stainless steel volume 113.7 ft'.5 Off-Load Sequence Data (Reference 1) defueling rate 4 fuel assemblies/hour maximum 2.6 Core Data (Reference 1) fuel assemblies in core 217 rated thermal power 2700 Mwt length of fuel cycle 18 months number of core exposure times 3 cycles
Cale. for Tmnstcnt Tcmpcraturc nf Spent Fuel Pool F np Full Core (ale. ~o. ~!ECit408$
SARGENT '- LUNDY Oftioad Rev. 0 ENGINEERS X Safety.Related .'v'on-Safety. Related Page o of Client Florida Power and Li~Jtt Prepared by Project St. Lucic Unit 2 Revie>>cd by Date Proj..'v'o. 084774I 6 Equip. v'o.N/A Approved by Date System Code Subsystem Division File to.
2.7 Material Properties (Reference 1)
Material Specific Heat Density Btu/Ibm-'F Ibm/ft'tainless steel 0.11 488 zircaloy 0.071 409 UO~ 0.06 684 2.8 Evaporation Parameters (Reference 1) environmental wet bulb temperature 100'F environmental dfy bulb temperature 104 F 2.9 Water Properties (Reference 6)
Temperature Specific Heat Density oF Btu/Ibm-'F Ibm/ft'2.0 100 1.00 110 1.00 61.9 2.10 Spent Fuel Pool Pump Data (Reference 10) motor horsepower (per pump) 40 hp Flow Rate Efficiency gpm 1500 83%
1755 75 3.1 The power 'lost'ue to Inefficiencies of the spent fuel pool pump is assumed to be added to the spent fuel pool water as heat.
4 C'f
.alc. For Transrcnt Tcrnocraturc ot'Spent Fuel Pool F nc Full core Cate, %o. WIECll Air/'es.
S,rIIRGENT:s LUNDY omoad 0 ENGINEERS X Safcn-Related l'on-Safen-Related Pace . of Client Florida Pn>>cr and Lieht Prepared by Date Project St. Lucic Lrni( 2 Rcsie>>ed by Proj. No. 08477-Ol 6 Equip. Xo.!i/A Approved be Date Sys'tent Code Subsystem Division File!io.
The spent fuel pool water, which is borated. is assumed to be pure water for purposes of property determination. This is reasonable, since the boron occupies a small fraction of the spent fuel pool water volume.
3.3 The decay heat from the spent fuel assem61ies discharged during previous outages.is i assumed to be constant. In reality, the decay heat is exponentially decreasing as a function of time. This behavior is produced by the decay of the fission products and their daughter products in the spent fuel. After a few months in the pool, however, the decay heat is produced by radioactive decay of nuclei with long half-lives. Therefore, because the rate of decay heat generation will not change significantly over the course of the transient, it is conservatively assumed that the decay heat generation from the fuel discharged during previous outages is constant.
3.4 It is assumed that no make-up water is available, since there are no safety-related make-up systems. The calculation takes into account evaporation, which will reduce the spent fuel pool water inventory.
3.5 It is assumed that the spent fuel pool water density and specific heat is constant during the transient. For subcooled water at near-atmospheric pressures, the variation of density and specific heat with temperature is negligible.
3.6 The calculation assumes that the spent fuel pool water is well mixed, and that no temperature stratification exists. This is reasonable because of the flow induced by the spent fuel pumps.
Furthermore, the spent fuel racks are assumed to be in thermal equilibrium with the spent fuel pool water. This is reasonable since the spent fuel pool is well mixed.
3.7 Heat transfer due to convection from the pool surface and conduction through the pool walls is neglected. This is conservative because peak fuel pool temperature will be maximized.
These heat transfer mechanisms will provide only a small contribution to total heat loss, and therefore, have only a minor impact on the peak temperature.
The Pauker evaporation equation (Reference 8) is used to determine evaporative heat removal. This provides a more conservative (smaller) evaporative heat removal rate than the Carrier model.
3.9 The spent fuel pool ambient air pressure is assumed to be 14.696 psia for determination of spent fuel pool evaporation.
3.10 The spent fuel pool liner is conservatively ignored in determination of spent fuel pool thermal capacitance.
3.11 The thermal capacitance of the stainless steel, uranium dioxide and zircaloy cladding associated with the spent fuel is conservatively neglected since the fuel is hot prior to the start of '..".e transient.
alc. For Transient Temperature ot'Spent Fuel Pool F e Ful! Core Cate. So.! IECli40$ 8 SARGENT":. LUNDY Offloa Rcv. tt ENGtNEERS X Sarct!-Related Ion-Safety-Related Pace 8 ol'lient Florida Po>>er and Lieht Prepared by Date Project St. Lueie Unit 2 Revie>>cd by Date Proj. Xo. 084774l6 Equip. No.N/A Approved by Date System Code Subs! stem DiviYion file to.
4.0 APPROACH To determine the time dependent temperature of the water in the spent fuel poof. a heat balance analysis will be performed at each time interval following the initiation of defueling.
The heat balance takes into account the initial conditions of the pool at the start of the transient. the addition of heat from the decay of spent fuel and spent fuel pool pumping power, and the loss of heat from pool evaporation and heat exchanger operation. Decay heat from the spent fuel elements previously stored in the pool and the new elements added during the transient are included. An energy balance around the spent fuel pool coolant yields the following equation:
.dT dc
= 1 pvcFr
[q - q (c) + q. (c)- q (c),]
where:
T bulk pool temperature t time after discharge into pool pVc, thermal capacitance of pool and steel energy addition due to pump qtc energy removal by heat-exchangers energy addition due to decay heat qe energy removal due to evaporation 4.1.1 Decay Heat Load The decay heat as a function of time is computed based on the methodology of Reference 7.
The time function is expressed as a series of 11 exponential terms. The functional relationship is defined as follows: '
E t, ( 0 c ) = (1+@) (,
P c ) .
8 P
(, c0 + c 8 )
0 p0 p0
ale. For Trmsiem Te'mperature of Spent Fuel Pool Fol e I ull Core pale. 'vo. SIECI4>NS SARGENT:.. LUNDY Pgoad Rcv'. 0 ENGINEERS X Safetv-Related Von~iafety.Related Page O of Client Florida Potter and Light Prepared by Project St. Lueie Unit 2 Revie>>ed by Date Proj. Xo. 08477-0 I 6 Equip. vo.iV/A Approved by Date System Code Subsystem Division File io.
where:
P P
(~
'00.1~Ae c,} =
1 ~11
-ac, n ~ask%"}
1 0.598 1 772 x 10o 2 1.65 5.774 x 3 3.10 x 19'3 10'.743 4 3.87 . 6.214 x 10~
5 2.33 4.739 x 10" 6 1.29 4.810 x 10~
7 0.462 5.344 x 10~
8 0.328 5.716 x 10'r 9 0.17 1.036 x 10 0.0865 x 10~
10'.959 11 0.114 7.585 x 10.to t, = cumulative reactor operating time (sec) t, = time after reactor shutdown (sec)
P = decay power P, = normal operating power K = uncertainty factor = 0.2. 0 s t, < 10'ec 0.1; 10' t, s 10'ec
~
decay heat due to heavy elements (U-239 and N,-239) is determined by:
'The
/ac P =2. 17x10 P C G ras (1. 007
- 3. I 1xl0 C 3. C lxlu e
-c 91xlO co c.91xtO
~
cq
ale. For Transient Temperature of Spent Fuel Pool Fv ae Full Cor Cale. vo..'vlECH<%88 SstRGENT - LUNDY OtYtoad Rev. 0 h ~
ENGINEERS X Safety-Related Non.safety-Related Page l0 of Clic'nt Florida Power and Li8ht Prepared by Date Project St. Lucie Unit Reviewed by Date Io. 08477-0l 6 'roj.
Equip. Xo.N/A Approved by Date Svstem Code Subsvstem DiviYion .File!'o.
where:
PU239 decay heat due to U-239, MW PNo239 decay heat due to N,-239, MW C conversion ratio, atoms of Pu-239 produced per atom of U-235 consumed
<2S effective neutron absorption cross section of U-235, barns t7r2s effective neutron fission cross section of U-235, barns C o2si aas is conservatively taken to equal 0.7, as directed by Reference 7. The total heat toad due to fission products and heavy elements is determined by:
P coc =P+P rrztt +P srpzst where:
Total decay heat due to fission products and heavy elements for a full core 4.1.2 Heat Exchanger The energy removal term is replaced by the following heat-exchanger (Hx) equation per Kreith (Reference 4):
q= e'f'f. (T-T )
where:
e heat exchanger effectiveness f fouling reduction factor Cma minimum (m C,)
T spent fuel pool bulk temperature Tc Hx cold side inlet temperature m coolant mass flow rate Cp coolant specific heat 4.1.3 Evaporation The energy removal due to evaporation is determined using the following relationship from Pauker (Reference 8):
alc. For Trans)ent Tempcratu/e ot Spent Fuel Pool F ne Full Con; ('ale. io. iIEt."II40SS ARGENT = LUNDY ONoad Rcv. u ENGINEERS X Safety-Related ion-Safety-Related Page II of Client Florida Povvcr and Light Prepared by Date Project St. Lucie Unit 2 Reviewed by Date Proj..'fo. 08477-OI6 Equip. Xo>IA. Approved by Date System Code Subsystem Division File ((o.
= A [35. 0 (C -C }
' jt where:
A pool surface area (m')
CA = water vapor concentration in the atmosphere (kg/m')
Gv saturation vapor concentration at the pool surface pressure and temperature (kg/m')
h/o latent heat of vaporization at the pool surface temperature (J/kg) 4.1.4 Saturation Pressure The saturation pressure (for T~459.69'R) is calculated using an equation from Reference 5:
P = 29.921 x 10"'* " '"
where:
P saturation pressure (in Hg) pt A, (Z-1) pg Ag ln(Z)
Pa A (10(A (t.t/zj) 1)
Pa As(10(" '"-1) and A, -7.90298 5.02808
-1.3816 x 10'1.344 8.1328 x 10~
-3.49149 Z (T + 459.688)/1.8 4.1.5 Latent Heat of Vaporization The latent heat of vaporization is determined by the following equation from Reference 3:
8 11 n, =P cp, (ln (p ) )
P (:G (1n(p ) )
sno ]nO
ale. For Transtcnt Temperature of Spent Fuel Pool F nz Full Core Cate, No. MFCll t 088 GARGENT - LUNDY ENGtNEERS Pffi>>d X Safeh-Related l'on-Safety-Related Res. 0 Pape l'f Clfcnt Florida Power and Liaht Prepared by Date Project St. Lucic Unit 2 Reiic>>ed by Date Proj.. io. 084774 I6 Equip. fo.N/A *pproved by Date System Code Subsystem Disision File Iu.
where:
CFo 0.6970887859 x 102 CF, 0.3337529994 x 102 CF2 0 2318240735 x 10 CF3 0.1840599513 x CF, x 10'0.5245502284 CFa x 10'210'.2878007027 CFo 0.1753652324 x CF, x 10~
10'0.4334859629 CFB 0.3325699282 x 10~
CGo 0.1105836875 x CG, x 10'.1436943768 CG2 x 10 10'.8018288621 CGa 0.1617232913 x CG, x 10' 10'0.1501147505 CG5 CGo 0 CG, 0 CGo 0 CGo -0.1237675562 x 10~
CGto 0.3004773304 x 10~
CG -0.2062390734 x 10~
4.1.6 Humidity Ratio Humidity ratio (W) is determined from this equation from Reference 2:
W W =
W s
=
'a s t oa sg W
2
= 1093+0.444T Da -THa
ale. For Transient Temperature ot'Spent Foci Pool Fs nr. Full cure Calc, io. itECII 00SS SARGENT:.. LUNDY osd Res. 0 ENGINEERS Safeo-Related Ionkafets-Related Page 13 'uf Clisnr florida Poncr and Lieht Prepared by Date Project St. Lucie Unit 2 Realest cd by Date Proj. ~o. 08477.0I6 Equip. No.NIA Approved by Date S! stem Code Subsystem Division File.'io..
P NSN Pr = 0.62198 Ala NSN and WB saturated humidity at dew point temperature pmw saturated pressure at T~; psia TDB drybulb air temperature, 'F TwB wetbulb air temperature, 'F PAIR atmospheric pressure, psia 4.1.7 Partial P.essure of Steam at Dew Point Temperature Partial steam pressure at dew point temperature is calculated with the equation from Reference 2:
NSD 0.62198 + Pr where:
P~D Partial steam pressure at dew point temperature, psia 4.1.8 Concentration of Water Vapor in Air V
'Y The concentration of water vapor in the air is determined from this equation:"
P NSO x CNA P
Nsa, where:
GwA = density of saturated steam at T, Ibm/ft' P~B = saturation pressure at TDpsia 4.1.9 Heat Added to Spent Fuel Pool Due to Pump Inefftciencies Per Assumption 3.1, the power lost due to pump jneffjciencies is assumed to be added to the spent fuel pool water as heat. The following equation is used:
alc For Transient Temperature of Spent Fuel Pool F 'ull Core Cate. No. XIECII.LVSS ARGENT'- LUNDY Omoad Re'v, 0 ENGINEERS X Safety-Related %on-Safety. Related Pane la of Client Florida Pointer and Light Prepared by Date Project St. Lucie Unit 2 Revie>>ed by Date Proj. ~'o. 084774 l 6 Equip..'fo.N/A Approved by Date System Code Subsystem Division File .io.
where:
= brake horsepower of pump at operating point, hp
= pump efficiency at operating point, %
The transient spent fuel pool temperature is computed using the S&L validated and verified computer program FPT (Program Number 03.7.244 Version 1.2). The controlled copy is stored in the S&L Computer Software Library. The program was run on a P5-120 personal computer. Input which involved computation is detailed below.
5.1 Thermal Capacity and Volume of Solid Materials ln Spent Fuel Pool The program takes into account the thermal capacity of the solid material in the pool. The programuses the term steel, but the thermal capacity ofany material can be inputted. The pool contains stainless steel fuel racks and the fuel, which consists of zircaloy, stainless steel, and uranium dioxide. Since the fuel is hot, it is not taken credit for in the thermal capacity.
The total volume of solid material in the pool is of interest since it deducts from the volume of water in pool. The total volume of the solid material in the pool is determined below:
Object Material Mass Density (m) Ibm/ft'olume (p) (m/p)
Ibm ft Fuel (Total) UO, 825,273, 684 1,206.5 Fuel (Total) Zircaloy 236,300 409 577.8 Fuel (Total) S. Steel 46,754 488 95.8 Fuel Racks S. Steel N/A 488 1952.5 Total 3832.6
.sic. For Trsnsicnt Tentpcnture nf Spent Fuel Pool Fo ie Full Cure Cslt. No. Itscl tw%5S SARGENT .: LUNDY Otllosd Rcv ~ d ENGINEERS X Ssfcty.Rclsted Ion.ssfcty-Relsted Psec IS of Clie'nt Florid>> Pouer end Light Prepsred by Date Project St. Lucie Unit 2 Revie>>ed by Dste Proj~ >>to. 084774I 6 Equip.,'fo.N/A Approved by Dste System Code Subsystem Division File v'o.
Vo1ume oi Vates = Volume oi Pool - Volume oi Sonics 45'69 fC 3r 833 fC
= 42, 136 ft 5.3 Spent Fuel Pool Heat Load Reference 1 identifies the decay heat load of the core and spent fuel. Since the program FPT determines decay heat load'per the methodology specified in Branch Technical Position ASB 9-2 (Reference /), and there is no capability to explicitly input the heat load into the program, input values of reactor thermal power and fuel assembly exposure time must be adjusted to obtain the desired heat loads.
Cases 1 through 5 involve one of two different discharge schemes - full core and partial core.
For both discharge scenarios, the input parameters used by FPT to determine heat load due to these 'new assemblies'n the spent fuel pool - reactor thermal power and exposure time of fuel assemblies in the core were adjusted so that the resulting heat load determined by FPT bounds the decay heat load given in Reference 1.
For the case 3, which involved partial core oNoads, (since defueling is interrupted to prevent the spent fuel pool from exceeding 140'F) the fuil core heat load given in Reference 1 was multiplied by the ratio of fuel assemblies discharged to the fuel assemblies in a full core. The number of fuel assemblies oNoaded was determined from trial and error. This prorated heat load was then bounded by the heat loads used. in FPT for these cases.
The comparison of given heat loads and utilized heat loads is shown below and in Figures 6 and 7. As can be seen below, the decay heat load used in the calculation is slightly higher than the heat load calculated in Reference 1. This is conservative, since a higher heat load will increase the peak temperature of the spent fuel pool.
Ca le. For Transient Temperature of Spent Fuel Pool F ng full Core Calc. No MECil<Vglt
&ARGENT:- LUNDY offload Rev. 0 ENGINEERS X SafeD-Related 4onaafety-Related Pane 16 of Chent Florida Po>>cr and Light Prepared by Date Project St. Lucie Unit 2 Revie>>ed by Date Proj. l'o. 03477-016 Equip. v'o.N/A Approved by Date Svstcm Code Subsystem Division file io.
Full Core Heat Load - Cases 1. 2. 4. 5 Time After Decay Decay Time After Decay Decay Shutdown Heat Load Heat Load Shutdown Heat Load Heat j.oad Per Ref 1 Used Per Ref 1 Used'ours x 10'TU/hr Hours x 10'TU/hr 100 34.41 34.48 210 25.04 25.09 105 33.68 33.74 220 24.58 24.63 110 32.99 33.06 230 24.16 24.21 115 32.35 32.42 240 23.76 23.81 120 31.75 31.81 250 23.39 23.43 125 31.18 31.24 260 23.03 23.08 130 30.65 30.71 270 22.70 22.75 135 30.14 30.20 280 22.39 22.43 140 29.67 29.73 290 22.09 22.13 145 29.22 29.28 300 21.80 21.85 150 28.79 28.85 310 21.53 21.57 155 28.39 28.45 320 21.26 21.31 160 28.01 28.07 330 21.01 21.05 165 27.65 27.70 340 20.81
'0.77 170 27.30 27.36 350 20.53 Not Used 175 26.97 27.03 360 20.30 Not Used 180 26.66 26.71 370 20.08 Not Used 190 26.07 26.12 380 19.87 Not Used 200 25.53 25.59 390 19.66 Not Used
Cele. For Transient Tctnpcraturc orspent Foci Pool F nr. I'ull core Csle. io. itECn A)SF
/ARGENT = LUNDY omoed Res. t<
ENGINEERS X Safety-Relmted .'ion-Sefeo-Related Pekoe 1 of Client Florid> Pointer and Lieht Prepared by Dete Project St. Lucic L'nit 2 Reeie~ed by Date Proj.. io. OS477.0l6 Equip. Io.N/A Approved by Date System Code Subsystem Division File %n.
Partial Core Offioad - Case 3
'I Time After Full Core Decay Time After Full Core Decay Shutdown Decay Heat Heat Load Shutdown Decay Heat Heat Load Load Per Ref Used Load Per Ref Used 1 X (160/217) 1 X (160/217)
(See Note) (See Note)
Hours x 10'TU/hr Hours x 10'TU/hr 100 25.37 25.42 210 18.46 18.50 105 24.83 24.88 220 18.12 18.16 110 24.32 24.38 230 17.81 17.85 115 23.85 23.90 240 1?.52 17.55 120 23.41 23.46 . 250 17.25 17.28 22.99 23.04 260 16.98 17.02 130 22.60 22.64 270 16.74 16.77 135 22.22 22.27 280 16.51 16.54 140 21.88 21.92 290 16.29 16.32 145 21.54 21.59 300 16.07 16.11 150 21.23 21.27 310 15.87 15.90 155 20.93 20.98 320 15.68- 15.71 160 20.65 20.69 330 15.49 15.52 165 20.39 20.43 340 15.31 15.34 170 20.13 20.17 350 Not Used Not Used 175 19.89 19.93 360 Not Used Not Used 180 19.66 19.70 370 Not Used Not Used 190 19.22 19.26 380 Not Used Not Used 200 18.82 18.87 390 Not Used Not Used Note: The numb er of fuel assemblies offioade d, 160, was determined by an iterative a pproach. Give n the initial conditions, this is t he maximum number of fuel assemblies that can b e offioaded without the fuel pool peak temper ature exceeding 140'F. At the time that the
Calc. for Ttanstcnt Temperature of Spent Fuel Pool f 'mg Full Cvte Cate..vo. XtEClt408S
'SARGENT LUNDY offload Rev. 0 ENGINEERS Safetv-Related .'v'on+afety-Related Page IS of Client Florida Povvcr and Light Prepared by Date Project St. Lucie Unit 2 Revie>>cd by Date Proj. v'o. 08477-0I 6 Equip. vto.'N/* *pproved by Date System Code Subsystcrn Division File vto.
160 th fuel assembly is moved to the fuel poof, the fuel pool temperature is 136.3'F. The peak pool temperature, which occurs 13.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> later, is 139.7'F.
After adjusting the inputs to obtain the proper core heat load, the existing spent fuel hed load was simulated. A multiple of the discharge was used, and the time that the discharged core decays in the spent fuel pool was varied until the value calculated bounded -the value given in Reference 1. The heat load used in the calculation is 2.378 x 10'tu/hr, which is greater than the valve of 2.37 x 10'tu/hr determined in Reference 1. This is conservative since a higher heat load will lead to a higher peak spent fuel pool temperature.
The inputs used and the resulting heat loads are documented in a separate runs, which assume that an instantaneous discharge occurs at 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />. The output is documented in Appendices 6 and H. It should be noted that the results are only used to document the benchmark of the heat loads.
5.4 Pump Heat Load For 1500 gpm flowrate, efficiency is 83% per Reference 10:
q= <<o hp)(1 - o.83)( )
3.929 x 10,', hp
= 17,307 Btu/hr/Pump For 1755 gpm fiowrate, efficiency is 75% per Reference 10:
- 0.75)( 1 Btu/hr-q = (40 hp)(1 )
3.929 x 1'0 .'. hp
= 25,452 Btu/hr/Pump
ale.'or Transient Tcmpcraturc nf Spent Fuel Pool F 0 lull Core C'alc. ~o. ~tFCll Ates r &ARGENT:. LUNDY OAload Rev, 0 ENGiNEERS X Safety-Related .'v'on.saferv-Related Page l9 of t
Cltent Florida Povvcr and Lieht Prepared by Date Project St. Lucic Unit 2 Reviewed by Date Proj. Io. 08477.016 Equip. XoXfA *pproved by Date System Code Subsystem Division File ~n.
6.0 ~RS~Ttp Appendices A through E and G through H contain the output files from the FPT program.
Appendices A through E contain the output for cases 1 through 5, respectively, while-Appendices and H contain the heat load benchmarks for the full core and partial core scenarios, respectively. The output begins with a listing of input data supplied by the user.
This is just an echo of the input data file that provides a record of specified input. The input copy is followed by an annotated summary of the input variables read by the program. This summary includes all of the values supplied by the input file and decay heat rates calculated for the spent fuel stored in the pool during previous refuelings. Atter the input summaries. the values of time, the number of fuel assemblies added to the pool, the pool temperature, and the various heat rate additions and subtractions are printed out for each time step. This data is also printed to a plot file. At the end of the transient, the maximum (peak) temperature and time of occurrence as well as the evaporation rate at the peak temperature is printed.
Graphs 1 though 5 are plots of the spent fuel pool temperature versus time for cases 1 through 5, respectively. The table below contains the results for cases 1 through 5. These results are valid only for the heat load given in Reference 1 and presented in Section 2.3, which corresponds to the Cycle 10 refueling outage (Reference 12).
Case Peak Temperature, 'F 137 151 139.7 147 138 Time of peak temperature (after initiation of 63 66.5 53.5 65.5 64.50 defueling), hours Evaporation rate at peak temperature, lbm/hr 349. 653 405 562 372 Heat removed by evaporation (based on 3.53 6.62 4.10 5.70 3.77 latent heat of vaporization of 1014 Btu/lbm), x 10s Btu/hr ONoad quantity, fuel assemblies 217 217 160 217 217 Initial spent fuel pool tempeiature, 'F 106 106 106 106 106 SFP Flow, gpm 3000 1500 1500 1500 1755 SFP heat exchanger shell side (CCW) inlet 100 v 100 100 100 95 temperature,'F
'.75 Heat exchanger effectiveness 0.488 0.694 0.694 0.709 In case 3, the core offload was ended at 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, after 160 fuel assemblies had been oNoaded. At this point, the spent fuel pool temperature was 136.1'F. The peak fuel pool temperature, which
alc. For Ttanstcnt Temperature of Spent Fuel Pool Ful e full Core ('ale. io. itEI:H40IIS r
+t I
'ARGENT:-. LUNDY ONoad Rev. tI ENGINEERS Safety. Related Ion-safen.Related Page .'0 of / tg'gt Client Florida Po>>er and Lieht Prepared by Date Project St. Lucic unit 2 Revic>>ed by Date Proj..'io. 03477-016 Equip. co.N/p Approved by Date Svstem Code Subsvstem Division File Io.
occurred 13.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> later, was 139.7'F.
- 1. Calculation PSL-2FSM-97-001 Revision 0, "Design Inputs For Analysis of Spent Fuel Pool
~
Cooling System for S & L Unit 2 Core Off Load Transient Analysis, Transmitted Per Letter ENG-SPLS-97-0053, From C. R. Bible, FPL Engineering Manager to S. D Malak, S & L, dated 2/14/97, "St Lucie Plant Unit 2 Transmittal of Design Inputs Fife: PC/M 96172."
- 3. "RETRAN-02, A Program for Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems," Volume 1, July 1981.
- 4. Krelth, F., "Principles of Heat Transfer," 3rd edition, International Textbook Company, 1965.
- 5. Tamami Kushuda, "Algorithms for Psychometric Calculations," National Bureau of Standards Report No. 9818, March 1, 1969, Washington, DC.
- 6. "Thermodynamic Properties of Steam," Kennan, J. H., Keyes, F..G., First Edition, 20th Print'ng, 1949.
- 7. NUREG-0800, Section 9.2.5, Branch Technical Position ASB 9-2,"Residual Decay Energy for Light Water Reactors for Long Term Cooling," Rev. 2, July 1981.
- 8. "A Novel Method for Measuring Water Evaporation into Still Air," Pauker, M. T., et. al., V. 99, Pt.
1, ASHRAE Transactions 1993.
- 9. FPT Spent Fuel Pool Bulk Temperature Program User Manual, Pichurski, D. J., Program Number 03.7.244-1.2.
- 10. Vendor Manual 28894088, Transmitted Per Letter ENG-SPLS-97-0053, From C. R. Bible, FPL Engineering Manager to S. D Malak, S & L, dated 2/14/97, "St Lucie Plant Unit 2 Transmittal of Design Inputs File: PC/M 96172. (Attached)
- 11. Calculation PSL-2FSM-97-004, Revision 0, "St. Lucie Unit 2 Spent Fuel Pool Heat Exchanger Performance," Transmitted Per Letter ENG-SPLS-97-0053, From C. R. Bible, FPL Engineering Manager to S. D Malak, S & L, dated 2/14/97, "St Lucie Plant Unit 2 Transmittal of Design Inputs File: PC/M 96172.
- 12. Letter ENG-SPLS-97-0058, From C. R. Bible, FPL Engineering Manager to S. D Mafak, S & L, dated 2/17/97, "St l.ucie Plant Unit 2 Transmittal of Design Inputs File: PC/M 96172.
APPENDIX F Graphs Gale No.: MECH-0088 Revision: 0 Project No.: 08477-016 Page F1
Appendix F Figure 1: Spent Fuel Pool Temperature For Case 1 (2 SFP Pumps) 140 135 130
- 125.
3 E 120 I
0 0
o- 115
- 5. 110 Ol 105 100 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300
'Hme After Initiation of Oefuellng, hours CALC.MECH4088 REV. 0 PROJECT NUMBER 08477.
SAFETY RELATED APPENDIX F, PAGF F2
Appendix F Figure 2: Spent Fuel Pool Temperature For Case 2 (1 SFP Pump, Fouled HX, and Design Flows) 155 150 145 I 140 .
135 ~
8 130.
I- 125 ~
O 0
120 .
g 115 110 105 100 20 40 60 80 100 120 140 160 180 200 220 240 260 280 3QQ .
Time After initiation of Oefuellng, hours GALG.MECH-M88 REV. 0 PROJECT NUMBER 08477%16 SAFETY RELATED APPENDIX F. PAGE F3
. ~ 9'I Appendix F Figure 3: Spent Fuel Pool Temperature For Case 3 (Offload Stopped To Prevent Pool From Reaching 140 degrees F.)
140 .
135 130 125
~ 120.
E I-0
~0 115
~4 C
- a. 110 CO 105 100 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 Time After tnltlatlon of Defueling, hours CAI.C.MECH.0088 REV. 0 PROJECT NUMBER 08477 " I SAFETY RELATED APPENDIX FPAGE F4
s I
Appendix F Figure 4: Spent Fuel Pool Temperature For Case 4 (5 SFP Pump, Glean HX, Design Flows) 150 145 140-I 135 8 130 P4 E< 125 o 120.
115 .
110 105 100 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 Time After Initiation of Defueling, hours CALC.MECHZ088 REV. 0 PROJECT NUMBER 08477%16 SAFETY RELATED APPENDIX F, PAGE F5
Appendix F Figure 5: Spent Fuel Pool Temperature For Case 5 (1 SFP Pump, Clean HX, Increased SFP Flow) 140 135 .
130
- 125.
P.
E 120 I-O 0
- o. 115
- a. 110.
V) 105 100 .
0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 Time After Initiation of Defueling, hours CALC.MECH@088 REy. 0 PROJECT NUMBER 08477<
SAFETY RElATED APPEND)X F PAAF F6
Appendix F Figure 6: FuJI Core Heat Load Benchmark 3.600E+07 3.400E+07 3.200E+07 3.000E+07 fQ 2.800E+07 Used ln Calculation Per Reference 1 2.600E+07 .
2.400E+07 .
2.200E+07-2.000 E+07 100 120 140 160 180 200 220 240 280 280 300 320 340 Time After Reactor Shutdown, hours CALC.MECH4088 REV. 0 PROJECT NUMBER 0847718 SAFETY REINED APPENDlX F, PAGE F7
Appendix F Figure 6: Partial Core Heat Load Benchmark
~
2.600E+07 2.500/+07 2.400E+07-2.300E+07 .
2.200E+07 .
m 2.100E+07 Used In Calculation Per Reference (Prorated) 0 1
-I 2.000E+07 X
1.900E+07 .
1.800E+07 .
1.700E+07 .
1.600E+07 .
1.500E+07 100 120 140 160 180 200 220 240 280 280 300 320 340 Tfme After Reactor Shutdown, hours CALC.MECH@088 REV. 0 PROJECT NUMBER 084~418 SAFETY RELATED APPENDIX F, PAGE F8 ~ i nllr.
C) f~, e t
I