ML20033G869

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Rev 0 to Core Operating Limits Rept,Cycle 2
ML20033G869
Person / Time
Site: Fermi 
Issue date: 12/21/1989
From: Shie-Jeng Peng, Rashid P, Westover T
DETROIT EDISON CO.
To:
Shared Package
ML20033G850 List:
References
COLR-2, COLR-2-R, COLR-2-R00, NUDOCS 9004120248
Download: ML20033G869 (20)
v • d • e


Text

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COLR>t Revisi:10 Pete 1 of 20 FERRI t C0kt OPERATING LIMITS MPORT CYCLE t k

1 C

Prepared by:

M 13/P e M

. Rashid

'Date Senior Engineer Reactor Physics Reviedeo by:

y WAw d ll 12 l11/79 T. L. Wes'tover D6te Associate Engineer Reactor Physics

/8/8//4 e

Reviewed by:

f I

Date/

5. J. P(K (hersal@ydraulics Engineer T

14/8ilff Approved by:

A.D.Strt Date General Supervisor Nuclear Fuel 9004120248 900326 DR ADOCK 0500 : 1 gggggg gggg b

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00LR>t Revision 0 e-Pope i of 30 I

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TABLE 0F CONftNTS I

4 l

SECTION PAGE l

1.0 INTR 000CT!0N AND Sup0ERY 5

l 2.0 AVEMet PLANAR LINEAR NEAT SENEMTION MTE 6

I 2.1 Definition t.!

Dettmination of APLH6R Limit j

MINIMUM CRITICAL POWER MTIO ll I

l 3.0

)

3.1 Definition

[

]

3.2 Detemination of Operating Limit MCPR 1

3.2.1 Calculation of f i

3.2.2 Calculation of N j

3.t.3 Calculation of Operating Limit MCPR I

t 4.0 LINEAR HEAT SENEMTION MTE 19 4.1 Definition i

4.2 Determination of LH6R Limit j

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5.0 REFERENCES

20

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._. _ _____ _.... _ _ _._ ___._ _ __ __ _ ____ _ _.7__

<L 00LR>t Revision 0 Jl Pete 8 cf to 1

1

\\

l LIST OF FIGURES l

l PAGE Fleutt I

1 EXIMUM AVf%GE PLANAR LINEAR HEAT SENERATION ETt (EPLNGR) 7 l

l VER$US AVE MGE PLA E R EXP050RE, FUEL TYPt DCR183 t

t EXIMUM AVERAGE PLANAR LINEAR HEAT SENERATION RATE (EPLHGR) 8 l

l VER$U$ AVERAGE PLANAR [XPOSURE, FUEL TYPE SCR233 j

i j

3 MAXIMUMAVERAttPLANARLINEARHEATSENERATIONRATE(EPLNGR) 9 VER$U$ AVERAGE PLANAR EXPOSURE, FutL TYPE SC!!PD 4 MAXIMUM AVERA4[ PLANAR LINEAR HEAT RENERATION RATE ( E PLNGR) 10 t

VER$U$ AVERAGE PLANAR EXPO $URE, FUEL TYPE SC318E i

5 BOC 70 !!,700 MWD /$T, OPERATING LIMIT MINIMUM CRITICAL 15 l

t i

PWER RATIO (0LMCPR) VER$US f AT RATED FLW i

l 6 12,700 MWD /$T TO 13,700 MWD /$T, OPERATING LIMIT MINIMUM 16 CRITICAL POWER RATIO (0LMCPR) GR$U$ f AT RATED FLW 7 13,700 MWD /$T 70 E00, OPERATING LIMIT MINIMUM CRITICAL 17 i

l POWER RATIO (0LMCPR) VER$U$ f AT RATED FLW 8 FLW CORRECTION (4) FACTOR 18 i

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00LRot bevision 0 Page 4 of 03 4.187 0F TABLES TABLE PAtt 1

FLW CORRtCTION FAC10R C0tFFit!!NTS 13 t

LM R LIMITS FOR VARIOUS Full TYPts 19

______J

00LRit Revision 0 Pope 6 of to 3.9 IWfR000CTIM AfD SWONY This report provides the cycle specific plent operating limits for Forst t Cycle I as required by Technical Specification 6.9.3. The entlytical methods used to determine these core operating limits are these previously reviewed end approved by the Nuclear Regulatory Commission in SE$ TAR !! Reference 1). These methods were used to ponerate the lietts in this report whi(ch are contained in Reference t.

OPERATING LINIT TECW ICAL SPECIFICATI M APLHGR 3/4.t.1 MCPR 3/4.t.3 LHGR 3/4.t.4 APLHGR = AVERAGE PLANAR LINEAR HEAT SENERATION RATE MCPR

= MINIMUM CRITICAL POWER RATIO LHGR

= LINEAR HEAT GENERATION RATE l

1

00LRat bevision 0 4

Page 8 of to

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8.0 AVERAtt MAMR LIMAR lEAT GMERAfl0N RATE TECN SPEC IDENT OPERATIN8 LIRlf FIGRES 3/4.2.1 APLHGR 1, t, 3,* A t.1 Definition The AVERAlt PLANAR LINEAR HEAT SENERATION RATE (APLNGR) shall be applicable to a specific planer heteht and is equal to the sum of the LINEAR HF.At stNERATION RATil for all fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.

,t.t Detereinstion of APLH8R Limit The APLHGR limits are a function of fuel type and average planer exposure. The limits are developed to ensure cross cladcine failure will not occur following a loss of coolant accident (LOCA).

The APLhGR limit ensures that the steady state power level in the fuel bundle duri a LOCA will not exceed a peak clad 3

temperature as specified in 10CFR50.46(b)

).

Figures 1, t, 3 and 4 contain the APLHGR limits for each fuel type as a unction of average pkanar exposure.

Since fuel types may contain more than one lattice type (exially), the curves represent the most limiting lattice type for that fuel type.

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b-OWRIST KWIFT 9.2 12.0 1,9 12.1 5.9 12.7 19.9 12.9 94_

15.9 12.9 29.9 12.7 25.0 11.7 39.9 19.9 13-i s.r

  • e.F e e.s s s.f 12-

.e 80APLMOR PERGSOSSAGE.E (KW/FT) 53E90008 OF OPERATION 99_

10-g O

5 mrERASE PLA00AR EXPOSIN3E (OWD/ST)

II

%b

~4 agaxonegas mEnaoE PLAesAn Les0 EAR MEM OE80ERM9008 RME (RSAPLMORS

.y VERSUS MERAGE PLANAR EXPOSURE.

"3 FUEL TYPE SCR183 3 =,

8 FDGtMIE 1 E._A_

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SWDIST KW#FT O.0 12.02 1.9 12.14 5.0 12.93 8.0 13.2s 14 10.9 13.34 18.8e s8.se i s.te 12.5 13.33 vs.or 93 _ t r.es 15.o 13.e2 25.e 11.7s 46.9 9.96 12' r.'e t#

59.9 8.64 s s.rs 11 10 PD M RE e.e, RIAPLMOR MEG 4000 OF p

OPERAT9006 (RWIFT) 8 I

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5 10 15 20 25 30 35 40 45 50 55 AFERAGE PLA08AR EXPOSURE (9WO/ST) gg Ib MAXIMUM MERAGE PLANAR LINEAR MEAT GE98ERMION RATE (esAPLHOR)

%I VERSUS MERAGE PLAMAR EXPOSURE.

1 FUEL TYPE SC3180 g,

8 FfGURE 3 o

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GWD/ST KWpFT i

O.0 11.99 i

i 1.0 12.10 l

5.0 12.79 l

14 r-e.o 13.15 j

1 is.se t s.sr 10.0 13.34 i

ts.se is.or 12.5 13.32 13 -**7' i s.o 13.02 rs.o 11.7s s t.rs 4 s.0 9.94 l

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50.0 9.83

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REG 80N OF i

(KW/FT)

OPERATION i

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10 15 20 25 30 35 40 45 50 55 i

l MERAGE PLANAR EXPOSURE (GWD/ST)

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MAXIMUM MEP. AGE PLANAR LINEAR HEM GENERMION RATE (MAPLHOR)'

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VERSUS MERAGE PLANAR EXPOSURE,

%f1 FUEL TYPE BC318E 3;;

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FIGURE 4 o

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Page 11 of to j

i 3.0 RINimm CRITICAL POWER RATI4 i

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TECH $ptC IDENT 9PERATINB LIMIT FleURsl i

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l 3/4.2.3 MCPR 5, 6, 7, 8 l

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f 3.1 Definition l

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The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in the assembly l

which is calculated by application of an NRC approved critical power correlation i

(Reference 1) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

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The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR that exists i

in the core, j

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3.2 Determination of Operating Limit NCPR l

l The required Operating Limit MCPR (OLF.PK) at steady state rated flow operating l

conditions is derived from the established fuel cladding integrity Safety Limit i

MCPR of 1.07 and an analysis of abneraal operational transients. To ensure that i

the Safety Limit MCPR is not exceeded during any anticipated abnomal operational i

transient, the most limiting transients have been analyzed at three different l

l core average exposures to determine which will cause the largest reduction in j

CPR. The result is an Operating Limit MCPR as a function of exposure and r, and d

based on a predicted end of cycle (E00) exposure of 14,700 MWD /ST.

If the i

predicted EOC exposure is modified, the exposure range for each OLMCPR figure may need to be changed.

The purpose of the K, factor is to define operating limits at other than rated core flow conditions. The K, factor ensures that the safety Limit MCPR will not be violated during a slow flow increase transient.

l factor yields The applicable exposure dependent OLMCPR at rated flow times the K,3.5 and shown the required OLMCPR.

K is calculated usiro Equation 3.4 or graphically in Figure 8,,and 7 is calculate ^ ising Equation 3.1.

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COLRat Revision 0 Page it of to 8.t.1 Calculation of f The value of f shall be detemined within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the conclusion of each scram time surveillance test by using the following equations (f.,, - f )

Eq. 3.1 f=

73 f,

where, i

fa = 1.096 seconds, control rod average scram insertion time limit to notch 36 per Technical Specification 3.1.3.3, f,=0.813+1.65[

)l"0.018 Eq.3.2 n

I N, i=1 n

I N, f, tal Eq.3.3

f.,, =

n I N, 11 n = number of surveillance tests perfomed to date,{n the cycle.

N, = number of active control rods measured in the i surveillance

test, th ti = average scram time to notch 36 of all rods measured in the i surveillance test, and N = total number of active rods measured in Technical Specification 3

surveillance Requirement 4.1.3.2.a.

NOTE:

Set r equal to 1.0 prior to completion of the initial scram time measurements for the cycle in accordance with Technical Specification Surveillance Requirement 4.1.3.t.a.

Set r equal to 0.0 if f less than 0,0.

00LRrt Revision 0 Pete 18 of to

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l 3.2.2 Caleslation of K, i

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4 flow correction factor is shown in Figure 8.

However, the value of K, The K,be calculated by one of the following equations:

shall 4

1 For 4 M < WT s 10 M,

l K, = MAX [1.0, A + 8

  • WT / 100.0)

Eq.3.4 j

for WT s 4M, l

K,

[A + B

  • WT / 100.0 ) * [1.0 + 0.0032 * (40.0 WT))

Eq.3.5 i

where, I

j WT = Core Flow (Percent of Rated Flow), and I

A and B are given in Table 1.

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n TABLE 1 FLM CORRECTIM FACTOR COEFFICIENTS i

T l

Scoop Tube Mechanical A

B i

High Speed Stop Setpoint l

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Nanuel Flow 102.5%

1.3308 0.441 Control 107.M 1.3528 0.441 112.0%

1.3793

+0.441 1

117.M 1.4035 0.441 l

l Automatic Flow 1.4410 0.441 Control l

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00LR=2 Revision 0 c'

I Page 14 of 20 l

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l 3.t.3 Calculation of Operating Limit MCPR When the THilOEL POWER is greater than or eoual to 25% of RATt0 THilDEL POWER I

the Operating Limit MCPR is determined from Ngures 5, 6, or 7 as. follows:

j For operation in the centret tell care fcct) ou Pattem* the Operating

{

j A.

Limit MCPR is equal t's t te Curve A value for t ge 7 calculated according l

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to Equation 3.1 times the K, factor calculated according to the applicable i

Equation 3.4 or 3.5.

B.

For operation in the "- cartral call care thion.ttt) and Pattern *, the i

Operating Limit MCPR is equal to the Curve B value for tse r calculated l

l according to Equation 3.141mes the K, factor calculated according to the I

ePplicab e Equation 3.4 or 3.5.

j C.

For operation in either had Pattern

per Technical Specification 3.7.9, the Operating Limit MCPR is equal to i

)

the Curve C value for the 7 calculated according to Equation 3.1 tius the K, factor calculated according to the applicab e Equation 3.4 or 3.5.

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D.

For operation in either awl Pattern

factor calculated according to the applicable [quation 3.4 or 3.5.

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  • Two Rod Patt6rns are defined:

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The CCC (Control Cell Core) Red Pattern is operation with any rod pattern j

consistent with the following restrictions:

a.

A2 sequence and peripheral rods are unrestricted, i

b.

Al sequence rods must be between positions 36 and 48, inclusively.

c.

All other rods must be at either positions 46 or 48.

d.

Nomal control rod operability checks, coupling checks, scram time testing, ed friction testing of non CCC control rods do not require i

the utilization of the more restrictive non CCC Rod Pattern MCPR limits.

1 1.

The Non CCC Rod Pattern is operation with any other rod pattern.

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t COLT A Revisten 0 PopP. Il of 20

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1.2 1.3 i

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1.16 1.15 l

0 0.10.20.30.40.50.80.70.80.8 1 l

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CWVt A ICM liett for CCC ted Pettern with both turbine bypees and noteters esperator rWooter in service.

r 11elt for hon CCC Red Pettern with both turbine bypees and estature esperator CWVt B + MCM,.sie, in eer. tee.

i

,o CWYt C

  • MCM ltett for both CCC and hon CCC Red Potterns with either turbine bypees er motstyre l

esperator rehester est of service.

CWWE D MCM ltoit for both CCC and hon-CCC kod Petterne with both turbine bypees and noteture seperator reheeter out of service.

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DOC TO 12.700190/87 OPERATIM LIMIT NINIMUM CRITICAL POER RATIO (0UICPR)

VERSUS f AT RATED FLOW FItuRF 5

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COLA.I hevision 0 Page 16 ef 20 1.48 1.46 1.4 14

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A 1.07' cumv5 A 1.26 1.96 7

1.2 1.2 1.16 1.16 0 0.10.20. 0.40.60.40.70.00.9 1 7

CWV( A EPR llett for CCC ted Pettern with both tur6tne bypose end acteture seperator rehoster in service.

CRV( l. EPR llett for hen CCC had Petterm with both turbine bases and estature esperator rehmeter in servlee.

CWV( C + EPR llett for both CCC and.en-CCC ted Potterne with either turbine bypees er setetste esperater fehmeter evt of servlee.

C@VE D + 9.PR limit for both CCC and hen-CCC had Petterne with both turbine byptes and entstyre esperster rehester out of servlee.

12.700 BRfD/$T TO 18.700 IRfD/$T.

OPERATIIIS LIMIT MINilIUM CRITICAL P0tfER RATIO (0UICPR)

VER$U$ f AT RATED FLotl FIOURE 4-l a

COLA:t Revision 0 Page 17 Cf CJ 1

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J 1.45 1.45 I

I gynyg,p'1.4 1.4 i.se

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s.88 i cumvs c 1.s e 1.35 1.35

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cumys A.s M

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1.25 1.25 1

i 1.2 j

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1.15 1.15 l

0 0.10.20.30.40.50.60.70.80.9 1 l

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CURVE A + NCPR liett for CCC And Pettern with both turbine byptes and noteture seperator rehester in se, vies.

CtmVI p MCPR Itatt for hen CCC hed Pettern with both turbine bypese end meteture esperater

}

reheeter in service.

CURV! C + MCPR lloit fer both CCC and hen CCC ted Petterne with either turbine bypese er estature cepeteter resseter out of service.

CURVE D MCPR lloit fer both CCC and non-CCC had Petterne with both turbine bypese and estature f

espereter tohester eut Of servlee, j

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13.700181D/8T TO E0C j

OPERATINS LIMIT MININUM CRITICAL POWER RATIO (0UICPR)

VER$US f AT RATED FLOW FleURE 7 l

Ceut t Revision 0 i

Pope 18 of 20 l

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i AVT0MATIC FLOW CONTROL

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f WANUAL Flow CONTROL 1.1 i

I SCOOP TUBE SETPOINT CALIBRATION

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PO$fTIONED $UCH THAT FLCwuAX = 102.6%

= 107.0%

= n 2.0%

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= nt.0%

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20 30 40 50 60 70 80 90 100 CORE FLOW (%)

FLOW CORRECTION (K,) FACTOR t

FIGURE 8 I

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COLR=2 hovision 0 Pepe le of 20 1

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4.0 LINEAR M AT GEM RAfl0N RATE r

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I TECM SPEC IDEN SPERATING LIMIT j

I 3/4.2.4 LNGR a

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f 4.1 Definition The LINEAR HEAT GENERATION RATE (LHSR) shall be the heat generation per unit l

1ength of fuel red.

It is the integral of the heat flux over the heat transfer l

area associated with the unit length.

d i

i 4.1 Detereinstion of ultR Limit pellets and Zircaloy cladding are different I

The thermal expansion rates of 00*1',et could come into contact with the cladding the fuel pe

(

in that, during heatupIf the stress exceeds the yield stress of the cladding I

and create stress.

)

material, the cladding will crack. The LHSR limit assures that at any exposure, 1% plastic strain on the clad is not exceeded. This limit is a function of fuel type and is presented in Table 2.

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f TABLE t LHtR LIMITS FOR VAR 100$ FUEL TYPES t

)

FUEL TYPE LNGR LIMIT i

SCRit3 13.4 KW/FT SCR233 13.4 KW/FT l

BC318D 14.4 KW/FT sc31st 14.4 KW/r1 i

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teLRit Revision 0 Pete f.3 of to O

5.0 RUERENCES

' General Electric Standard Application for Reacter Fuel (6 ESTAR !!),' NEDE.

3.

240ll P A. Revision 9, September 1988.

l

' Supplemental Reload Licensing submittal for Femi Power Plant Unit i Reload 2.

1, Cycle 2, SE Nuclear Energy, 23A5949 Revision 0, March 1989.

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