Text

Rev 0 to MECH-0088, Transient Temp of SFP Following Full Core Offload
	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: ML17229A864;
References
	MECH-0088, MECH-0088-R00, MECH-88, MECH-88-R, NUDOCS 9809230152
	Download: ML17229A864 (38)
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Ger gene &l uncly CALcULATroNAxALYszs FOR Fr oaroA PowER~ LIGHT(FPL)

ST. LUczs STATzoN Urm 2 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

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.S Gale No. MECH-0088 Revision: 0 Page:

1 Safety Related: Yes.

Prepared by T. J. Blohm Reviewed by K Chan /

/7

'Date

~It~ I r CJl~

Date 2.~! 7 v

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

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~r SARGENT - LUNDY ENGINEERS'e.

For Transtcnt Temperature ofSpent Fuel Pool Fol

.'ull Core Oflload Cate. No. ~tfCH&tgg Rcv. 0 X

Safety.Related Von-Safety-Related Pace'f Client Flotidd Pointer and Light Project St. Lucie Unit 2 Proj. Vo. 084774l6 System Code Equip. Vo.V/A Subsystem Prepared by Reviewed by Approved by Division Date Date Date File Vo.

TABLEOF CONVENT

~ection

1.0 Purpose and Scope

2.0 Design Input 3.0 Assumptions 4.0 Approach 5.0 Calculations 6.0 Results 14 19 7.0 References 20 8.0 Appendices A.

B.

C.

D.

E.

F.

G.

H.

Computer Output for Case 1

Computer Output for Case 2 Computer Output for Case 3 Computer Output for Case 4 Computer Output for Case 5 Graphs

. Computer Output for Full Core Decay Heat Benchmark

. Computer Output for Partial Core Decay Heat'Benchmark i-35 i-35 I-33 i-35 i-35 1-8 i-29 i-29

S.tttRGENT.-

i UNDY, ENGJNEERS Safety-Related

.'ion-safety.Related Calc. For Transient Tetnperature ofSpent Fuel Pool F 8 l ull Core OtTload Late. No. ~tbClW$88 Rev. 0 pa-c a or Cliont Florida Po>>cr and Light Project St. Lucie Unit 2 Proj. Yo. 084774)6 System Code Equip. pro.lqlA Subsystem Prepared by Rcvie>>ed by Approved by Division Date Date Date 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 fullcore oNoad given in Reference 1, which corresponds to the Cycle 10 refueling outage (Reference 12).

Case Time after reactor shutdown for initiation of defueling, hours Offload quantity Initial spent fuel pool temperature, F

SFP heat excharlger shell side (CCW) inlet temperature,'F Number of SFP l'umps 168 full core, 106 100 168 full core 106 100 168 partial core 106 100 168 full core 106 100 168 full core 106 95 SFP Pump Flow (gpm)

CCW Flow (gpm) 3000 3560 1500

-3560 1500 1500 3560 3560 1755 3560 Heat Exchanger Effectiveness 0.488 0.694 0.694 0.75 0.709 Special conditions NIA N/A'IA 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 SFP Pump Flow (gpm)

CCW Flow (gpm)

Heat Exchanger Effectiveness

3000, 3560 0.488 2.

'500 3560 0.694 1500 3560 0.694 1500 3560 0.75 1755 3560 0.709

0

al<<For Transient TcmpcmtutcofSpcm Fuel Poet F mc Full Cv ARGENT - LUNDY P/flood ENGINEERS Cale.,'vo. XtECtWh188 Rev. 0 X

Safety-Related

.'v'on-Sa fcn. Related Pase 4

of Client Ffottdu Povvcr and Ltaht Project St. Lucic Unit 3 Proj. >o. 084'174l6 Svstern Code Equip YoN/A Subsystem Prepared by Reviewed b'v Approved by Division Date Date Date File Xo.

2.2 Spent Fuel Pool Data (Reference 1) surface area gross volume 1194 ft 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 Shutdown Hours 100 105 110 115 120 125 130 135 140 145 150 155 160 165 170 175 180 190 200 Decay Heat Load x 10'TU/hr 33.68 32.99 32.35 31.75 31.18 30.65 30.14 29.67 29.22 28.79 28.39 28.01 27.65 27.30 26.9'7 26.66 26.07 25.53 Time After Shutdown Hours 210 220 230 240 250 260 270 280 290 300 310 320 330

. 340

'350 360 370 380 390 Decay Heat Load x 10'TU/hr 25.04 24.58 24.16 23.76 23.39 23.03 22.70 22.39 22.09 21.80 21.53 21.26 21.01 20.77 20.53 20.30 20.08 19.87 19.66

UM 4 J

'ale. For Transtent Temperature of Spem <<el Pool Fol' Full Core SARGENT '. LUNDY Pflload ENGINEERS Cate. No. MKHits>SS Rev. 0 X

Safety-Related Son-Safety-Related Pane 6

of Client Florida Potter and Light Project St. Lueie Unit

'roj..'fo.

08477-0l6 System Code Equip. fo.N/A Subsystem Prepared by Revietved by Approved by Division Date Date Date File No.

2.4 Non-Water Materials In Pool (ReferhRcep ~-

2.4.1 Fuel Assemblies (Reference 1)

Spent Fuel Core'otal Weight ofZircaloy (Ibm)

Weight of Stainless Steel (Ibm)

Weight of UO, (Ibm) 174,509 34,747 612,231 61,791 12,007 213,042 236.300 46,754 825.273 2.4.2 Fuel Racks (Reference 1) material volume stainless steel 1952.53 ft 2.4.3 Liner (Reference 1) material volume type 304 stainless steel 113.7 ft'.5 Off-Load Sequence Data (Reference 1) defueling rate 2.6 Core Data (Reference 1) 4 fuel assemblies/hour maximum fuel assemblies in core rated thermal power length of fuel cycle number of core exposure times 217 2700 Mwt 18 months 3 cycles

SARGENT '- LUNDY ENGINEERS Cale. for Tmnstcnt Tcmpcraturc nfSpent Fuel Pool F np Full Core Oftioad (ale. ~o. ~!ECit408$

Rev. 0 X

Safety.Related

.'v'on-Safety. Related Page o

of Client Florida Power and Li~Jtt Project St. Lucic Unit 2 Proj..'v'o. 084774I 6 System Code Equip. v'o.N/A Subsystem Prepared by Revie>>cd by Approved by Division Date Date File to.

2.7 Material Properties (Reference 1)

Material Specific Heat Btu/Ibm-'F Density Ibm/ft'tainless steel 0.11 488 zircaloy UO~

0.071 0.06 409 684 2.8 Evaporation Parameters (Reference 1) environmental wet bulb temperature environmental dfy bulb temperature 100'F 104 F 2.9 Water Properties (Reference 6)

Temperature oF 100 110 Specific Heat Btu/Ibm-'F 1.00 1.00 Density Ibm/ft'2.0 61.9 2.10 Spent Fuel Pool Pump Data (Reference 10) motor horsepower (per pump) 40 hp Flow Rate gpm 1500 Efficiency 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 S,rIIRGENT:s LUNDY omoad ENGINEERS Cate, %o. WIECll Air/'es.

0 X

Safcn-Related l'on-Safen-Related Pace of Client Florida Pn>>cr and Lieht Project St. Lucic Lrni( 2 Proj. No. 08477-Ol 6 Sys'tent Code Equip. Xo.!i/A Subsystem Prepared by Rcsie>>ed by Approved be Division Date Date 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 willnot 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 willreduce 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 willbe maximized.

These heat transfer mechanisms willprovide 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 3.10 The spent fuel pool ambient air pressure is assumed to be 14.696 psia for determination of spent fuel pool evaporation.

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 ENGtNEERS Offloa X

Sarct!-Related Ion-Safety-Related Rcv. tt Pace 8

ol'lient Florida Po>>er and Lieht Project St. Lueie Unit 2 Proj. Xo. 084774l6 System Code Equip. No.N/A Subs! stem Prepared by Revie>>cd by Approved by DiviYion Date Date Date file to.

4.0 APPROACH To determine the time dependent temperature of the water in the spent fuel poof. a heat balance analysis willbe 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 1

.=

[q - q (c)

+ q. (c)- q (c),]

dc pvc Fr where:

T t

pVc, qtc qe bulk pool temperature time after discharge into pool thermal capacitance of pool and steel energy addition due to pump energy removal by heat-exchangers energy addition due to decay heat 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 '

P P

(t, c

) = (1+@) (, c ). (, c + c )

0 p

8 p

0 8

0 0

0

ale. For Trmsiem Te'mperature of Spent Fuel Pool Fol e I ull Core pale. 'vo. SIECI4>NS SARGENT:.. LUNDY Pgoad ENGINEERS X

Safetv-Related Von~iafety.Related Rcv'. 0 Page O

of Client Florida Potter and Light Project St. Lueie Unit 2 Proj. Xo. 08477-0 I6 System Code Equip. vo.iV/A Subsystem Prepared by Revie>>ed by Approved by Division Date Date File io.

where:

11 P

1 ~

-ac,

(~ c,}

= ~Ae P

'00.1 n

~ask%"}

1 2

3 4

5 6

7 8

9 10 11 0.598 1.65 3.10 3.87 2.33 1.29 0.462 0.328 0.17 0.0865 0.114 1 772 x 10o 5.774 x 10'.743 x 19'3 6.214 x 10~

4.739 x 10" 4.810 x 10~

5.344 x 10~

5.716 x 10'r 1.036 x 10'.959 x 10~

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

~

'The decay heat due to heavy elements (U-239 and N,-239) is determined by:

/ac G

P

=2. 17x10 P C (1. 007 ras

3. I1xl0 C

3. Clxlu e

-c ~ 91xlO co c.91xtO cq

h ~

SstRGENT

- LUNDY ENGINEERS OtYtoad X

Safety-Related Non.safety-Related ale. For Transient Temperature of Spent Fuel Pool Fv ae Full Cor Cale.

vo..'vlECH<%88 Rev. 0 Page l0 of Clic'nt Florida Power and Li8ht Project St. Lucie Unit

'roj.

Io. 08477-0l 6 Svstem Code Equip. Xo.N/A Subsvstem Prepared by Reviewed by Approved by DiviYion Date Date Date

.File!'o.

where:

PU239 PNo239 C

<2S t7r2s decay heat due to U-239, MW decay heat due to N,-239, MW conversion ratio, atoms of Pu-239 produced per atom of U-235 consumed effective neutron absorption cross section of U-235, barns 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

=P+P

+P coc rrztt 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 f

Cma T

Tc m

Cp heat exchanger effectiveness fouling reduction factor minimum (m C,)

spent fuel pool bulk temperature Hx cold side inlet temperature coolant mass flow rate 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 ENGINEERS ONoad X

Safety-Related ion-Safety-Related Rcv. u Page II of Client Florida Povvcr and Light Project St. Lucie Unit 2 Proj..'fo. 08477-OI6 System Code Equip. Xo>IA.

Subsystem Prepared by Reviewed by Approved by Division Date Date Date File

((o.

= A[35. 0 (C -C }'

jt where:

A CA Gv h/o pool surface area (m')

= water vapor concentration in the atmosphere (kg/m')

saturation vapor concentration at the pool surface pressure and temperature (kg/m')

latent heat of vaporization at the pool surface temperature (J/kg) 4.1.4 Saturation Pressure The saturation pressure (forT~459.69'R) is calculated using an equation from Reference 5:

P = 29.921 x 10"'*"'"

where:

P pt pg Pa Pa saturation pressure (in Hg)

A, (Z-1)

Ag ln(Z)

A (10(A (t.t/zj) 1)

As(10(" '"-1) and A,

Z

-7.90298 5.02808

-1.3816 x 10'1.344 8.1328 x 10~

-3.49149 (T + 459.688)/1.8 4.1.5 Latent Heat ofVaporization 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

GARGENT - LUNDY Pffi>>d ENGtNEERS X

Safeh-Related l'on-Safety-Related ale. For Transtcnt Temperature of Spent Fuel Pool F nz Full Core Cate, No. MFCll t 088 Res. 0 Papel'f Clfcnt Florida Power and Liaht Project St. Lucic Unit 2 Proj.. io. 084774 I 6 System Code Equip. fo.N/A Subsystem Prepared by Reiic>>ed by

pproved by Disision Date Date Date File Iu.

where:

CFo CF, CF2 CF3 CF, CFa CFo CF, CFB 0.6970887859 x 102 0.3337529994 x 102 0 2318240735 x 10 0.1840599513 x 10'0.5245502284 x

10'.2878007027 x 10'2 0.1753652324 x 10'0.4334859629 x 10~

0.3325699282 x 10~

CGo CG, CG2 CGa CG, CG5 CGo CG, CGo CGo CGto CG 4.1.6 Humidity Ratio 0.1105836875 x 10'.1436943768 x

10'.8018288621 x 10 0.1617232913 x 10'0.1501147505 x 10' 0

0 0

-0.1237675562 x 10~

0.3004773304 x 10~

-0.2062390734 x 10~

Humidity ratio (W) is determined from this equation from Reference 2:

W W =

W s

=

'a s

t oa sg W

= 1093+0.444T

-T 2

Da Ha

ale. For Transient Temperature ot'Spent Foci Pool Fs nr. Full cure Calc, io. itECII 00SS SARGENT:.. LUNDY osd ENGINEERS Safeo-Related Ionkafets-Related Res. 0 Page 13

'uf Clisnr florida Poncr and Lieht Project St. Lucie Unit 2 Proj. ~o. 08477.0I6 S! stem Code Equip. No.NIA Subsystem Prepared by Realest cd by Approved by Division Date Date Date File.'io..

P Pr

= 0.62198 NSN Ala NSN and WB pmw TDB TwB PAIR saturated humidity at dew point temperature saturated pressure at T~; psia drybulb air temperature, 'F wetbulb air temperature, 'F 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 ofWater Vapor in Air V

'Y The concentration ofwater vapor in the air is determined from this equation:"

NSO NA P

x C

PNsa, where:

GwA P~B

= density of saturated steam at T, Ibm/ft'

= 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 ENGINEERS Omoad X

Safety-Related

%on-Safety. Related Re'v, 0 Pane la of Client Florida Pointer and Light Project St. Lucie Unit 2 Proj. ~'o. 084774 l 6 System Code Equip..'fo.N/A Subsystem Prepared by Revie>>ed by Approved by Division Date Date Date 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&Lvalidated 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)

(p)

Ibm Ibm/ft'olume (m/p) ft Fuel (Total)

UO, Fuel (Total)

Zircaloy 236,300 409 825,273, 684 1,206.5 577.8 Fuel (Total)

S. Steel Fuel Racks S. Steel Total 46,754 N/A 488 488 95.8 1952.5 3832.6

SARGENT.: LUNDY ENGINEERS

.sic. For Trsnsicnt Tentpcnture nfSpent Fuel Pool Fo ie Full Cure Otllosd Cslt. No. Itscl tw%5S Rcv ~ d X

Ssfcty.Rclsted Ion.ssfcty-Relsted Psec IS of Clie'nt Florid>> Pouer end Light Project St. Lucie Unit 2 Proj~ >>to. 084774I 6 System Code Equip.,'fo.N/A Subsystem Prepsred by Revie>>ed by Approved by Division Date Dste Dste 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 willincrease the peak temperature of the spent fuel pool.

Ca le. For Transient Temperature ofSpent Fuel Pool F ng full Core Calc. No MECil<Vglt

&ARGENT:- LUNDY offload ENGINEERS X

SafeD-Related 4onaafety-Related Rev. 0 Pane 16 of Chent Florida Po>>cr and Light Project St. Lucie Unit 2 Proj. l'o. 03477-016 Svstcm Code Equip. v'o.N/A Subsystem Prepared by Revie>>ed by Approved by Division Date Date Date file io.

Full Core Heat Load - Cases

1. 2. 4. 5 Time After Shutdown Decay Heat Load Per Ref 1 Decay Heat Load Used Time After Shutdown Decay Heat Load Per Ref 1 Decay Heat j.oad Used'ours 100 105 110 34.41 33.68 32.99 x 10'TU/hr 34.48 33.74 33.06 Hours 210 220 230 25.04 24.58 24.16 x 10'TU/hr 25.09 24.63 24.21 115 32.35 32.42 240 23.76 23.81 120 125 130 135 140 145 150 155 160 165 170 175 180 190 200 31.75 31.18 30.65 30.14 29.67 29.22 28.79 28.39 28.01 27.65 27.30 26.97 26.66 26.07 25.53 31.81 31.24 30.71 30.20 29.73 29.28 28.85 28.45 28.07 27.70 27.36 27.03 26.71 26.12 25.59 250 260 270 280 290 300 310 320 330 340 350 360 370 380 390 23.39 23.03 22.70 22.39 22.09 21.80 21.53 21.26 21.01

'0.77 20.53 20.30 20.08 19.87 19.66 23.43 23.08 22.75 22.43 22.13 21.85 21.57 21.31 21.05 20.81 Not Used Not Used Not Used Not Used Not Used

Cele. For Transient Tctnpcraturc orspent Foci Pool F nr. I'ull core Csle. io. itECn A)SF

/ARGENT = LUNDY omoed ENGINEERS X

Safety-Relmted

.'ion-Sefeo-Related Res.

t<

Pekoe 1

of Client Florid> Pointer and Lieht Project St. Lucic L'nit 2 Proj.. io. OS477.0l6 System Code Equip. Io.N/A Subsystem Prepared by Reeie~ed by Approved by Division Dete Date Date File %n.

Partial Core Offioad - Case 3 Time After Shutdown Full Core Decay Heat Load Per Ref 1 X (160/217)

(See Note)

Decay Heat Load Used Time After Shutdown Full Core Decay Heat Load Per Ref 1 X (160/217)

(See Note)

'I Decay Heat Load Used Hours 100 105 110 115 120 130 135 140 145 150 155 160 165 25.37 24.83 24.32 23.85 23.41 22.99 22.60 22.22 21.88 21.54 21.23 20.93 20.65 20.39 x 10'TU/hr 25.42 24.88 24.38 23.90 23.46.

23.04 22.64 22.27 21.92 21.59 21.27 20.98 20.69 20.43 Hours 210 220 230 240 250 260 270 280 290 300 310 320 330 340 18.46 18.12 17.81 1?.52 17.25 16.98 16.74 16.51 16.29 16.07 15.87 15.68-15.49 15.31 x 10'TU/hr 18.50 18.16 17.85 17.55 17.28 17.02 16.77 16.54 16.32 16.11 15.90 15.71 15.52 15.34 170 175 180 190 200 20.13 19.89 19.66 19.22 18.82 20.17 19.93 19.70 19.26 18.87 350 360 370 380 390 Not Used Not Used Not Used Not Used Not Used Not Used Not Used Not Used Not Used Not Used a

b er of fuel assemblies offioade n the initial conditions, this is t out the fuel pool peak temper Note: The numb pproach.

Give e offioaded with d, 160, was determined by an iterative he maximum number of fuel assemblies that can ature exceeding 140'F. Atthe time that the

Calc. for Ttanstcnt Temperature of Spent Fuel Pool f

'mg Full Cvte

'SARGENT "- LUNDY offload ENGINEERS Cate..vo. XtEClt408S Rev. 0 Safetv-Related

.'v'on+afety-Related Page IS of Client Florida Povvcr and Light Project St. Lucie Unit 2 Proj. v'o. 08477-0I 6 System Code Equip. vto.'N/*

Subsystcrn Prepared by Revie>>cd by

pproved by Division Date Date Date 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 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 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 willlead 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 0.0278 hours 1.653439e-4 weeks 3.805e-5 months . 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:

1 Btu/hr-q =

(40 hp)(1 - 0.75)(

)

3.929 x 1'0

.'. hp

= 25,452 Btu/hr/Pump

r &ARGENT:. LUNDY ENGiNEERS ale.'or Transient Tcmpcraturc nfSpent Fuel Pool F OAload 0 lull Core C'alc. ~o. ~tFCll Ates Rev, 0 X

Safety-Related

.'v'on.saferv-Related Page l9 of t

Cltent Florida Povvcr and Lieht Project St. Lucic Unit 2 Proj. Io. 08477.016 System Code Equip. XoXfA Subsystem Prepared by Reviewed by

pproved by Division Date Date Date 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 Time of peak temperature (after initiation of defueling), hours Evaporation rate at peak temperature, lbm/hr Heat removed by evaporation (based on latent heat of vaporization of 1014 Btu/lbm), x 10s Btu/hr ONoad quantity, fuel assemblies Initial spent fuel pool tempeiature, 'F SFP Flow, gpm SFP heat exchanger shell side (CCW) inlet temperature,'F Heat exchanger effectiveness 137 151 139.7 63 66.5 53.5 349.

653 405 3.53 6.62 4.10 217 217 160 106 106 106 3000 1500 1500 100 v 100 100 0.488 0.694 0.694 147 138 65.5 64.50 562 372 5.70 3.77 217 217 106 106 1500 1755 100 95

'.75 0.709 In case 3, the core offload was ended at 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months , 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 fullCore r+t I

('ale. io. itEI:H40IIS

'ARGENT:-. LUNDY ENGINEERS ONoad Safety. Related Ion-safen.Related Rev. tI Page

.'0 of / tg'gt Client Florida Po>>er and Lieht Project St. Lucic unit 2 Proj..'io. 03477-016 Svstem Code Equip. co.N/p Subsvstem Prepared by Revic>>ed by Approved by Division Date Date Date File Io.

occurred 13.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 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 OffLoad 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."

2.

ASHRAE 1987 Handbook of Applications and ASHRAE 1985 Handbook of Fundamentals.

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 LightWater 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 140 Figure 1: Spent Fuel Pool Temperature For Case 1

(2 SFP Pumps) 135 130

- 125.

3 120 E

I 00o-115

5. 110 Ol 105 100 0

20 40 60 80 100 120 140 160 180 200 220 240 260 280 300

'Hme AfterInitiation of Oefuellng, hours CALC.MECH4088 REV. 0 PROJECT NUMBER 08477.

SAFETY RELATED APPENDIX F, PAGF F2

Appendix F 155 Figure 2: Spent Fuel Pool Temperature For Case 2 (1 SFP Pump, Fouled HX, and Design Flows) 150 145 140 I

135

~

8 130.

I-125

~

O0 120 g 115 110 105 100 20 40 60 80 100 120 140 160 180 200 220 240 260 280 3QQ Time Afterinitiation of Oefuellng, hours GALG.MECH-M88 REV. 0 PROJECT NUMBER 08477%16 SAFETY RELATED APPENDIX F. PAGE F3

. ~

9'I

Appendix F 140 Figure 3: Spent Fuel Pool Temperature For Case 3 (Offload Stopped To Prevent Pool From Reaching 140 degrees F.)

135 130 125 E~ 120.

I-00~

115

~4C a.

110 CO 105 100 0

20 40 60 80 100 120 140 160 180 200 220 240 260 280 Time Aftertnltlatlon of Defueling, hours CAI.C.MECH.0088 REV. 0 PROJECT NUMBER 08477 "

I SAFETY RELATED APPENDIX FPAGE F4

sI

Appendix F 150 Figure 4: Spent Fuel Pool Temperature For Case 4 (5 SFP Pump, Glean HX, Design Flows) 145 140-135 I

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 AfterInitiation of Defueling, hours CALC.MECHZ088 REV. 0 PROJECT NUMBER 08477%16 SAFETY RELATED APPENDIX F, PAGE F5

Appendix F 140 Figure 5: Spent Fuel Pool Temperature For Case 5 (1 SFP Pump, Clean HX, Increased SFP Flow) 135 130

- 125.

P.

E 120 I-O0o.

115

a. 110.

V) 105 100 0

20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 Time AfterInitiation 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 2.600E+07

Used ln Calculation Per Reference 1

2.400E+07 2.200E+07-2.000 E+07 100 120 140 160 180 200 220 240 280 280 300 320 340 Time AfterReactor 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 0-I 2.000E+07 X

1.900E+07

Used In Calculation Per Reference 1 (Prorated) 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 AfterReactor Shutdown, hours CALC.MECH@088 REV. 0 PROJECT NUMBER 084~418 SAFETY RELATED APPENDIX F, PAGE F8

~ inllr.

C) f~,

e t

I

ML17229A864

Text

1.0 Purpose and Scope

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