ML20099B450

Rev 1 to Fort Calhoun Station Cycle 14,Core Operating Limits Rept

ML20099B450
Person / Time
Site:	Fort Calhoun
Issue date:	06/28/1992
From:	Weber W OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20099B444	List: ML20099B440 ML20099B450
References
NUDOCS 9207310163
Download: ML20099B450 (14)

Text

g. .

,'.: 3 '. o'

. s'

• Fort Calhoun Station Unit No. 1 '

TDB-VI TECHNICAL DATA BOOK PROCEDURE

Title:

CORE OPERATING LIMIT REFORT =

u _

Setpoint/ Procedure Form-Number-(FC-68); 38746 b

Reason for Chango: Update Figures 3 and 5 and Item 6.0 Linear Heat Rate as noted in PED-FC-92-1395. (Memo)

Contact Person: William Weber ISSUED: 06-28-92 12:45 am R1 9207310163 920723

-POR ADOCK 05000285 P PDR

r .

++

FORT CALHOUN STATION TDB-VI

- TECHNICAL DATA.DOOK PAGE 1 OF .

4 4

L Fort Calhoun Station, Unit 1 '

Cycle 14 Core Operatina Limits Reop_ri

[ ' Due to the critical aspects of the safety analysis inputs

! contained in this report, changes may not be made to this report l - without concurrence of:the Production Engineering Division, Nuclear' Engineering Department, t

l I-t:

L I

l l5 R1 FC/TDB-

.' FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 3 OF 13 IdB._I OF TADAE Table No. Tills Paae 1 TM/LP Coefficients 6 2 Maximum F g and F xy Limits 7 FC/TDB R1

Ed

• h: . .

,.,j c,::FORTJCALHOUN STATION. TDB-VI TECHNICAL DATA-BOOK PAGE'l.OF 13 4

Fort Calhoun Station, Unit 1 Cycle 14~ Core Operatina Limits Report Due'to_the critical aspects of the safety analysis inputs contained in this report, chances:may not be made.to this report

~

without: concurrence'of the Production Engineering Division, Nuclear Engineering; Department.

4 i-i R1 FC/TDB

FORT CALHOUli STATIO!! TDB-VI '.

-TECH!i1 CAL DATA BOOK PAGE 2 OF 13

. TABLE OF CONTEN_TH lten Description Page 1.0 Introduction 5 2.0 Core Operating Limits 5 3.0 TM/LP Limit 6 4.0 Maximum Core Inlet Temperature 6 5.0 Power Dependent Insertion Limit 6 -

6.0 Linear Heat Rate 6 '

7.0- Excore Monitoring of LHR 7 8.0 Peaking Factor (F xy T, Fg) T Limits 7 9.0 D!lB-Monitoring 7 10.0. FgT, px T and Core Power Limitations 7 11.0 Refuel [ng Boron Concentration 7 FC/TDB R1

l FORT CALHOUN STATION TDB-VI l TECHNICAL DATA BOOK PAGE 4 OF 13 JJ, STS OF FIGURES Fiqure No. T_1.tle Paco 1 Thermal Margin / Low Pressure 4 Pump Operation 8 2 Power Dependent Insertion Limit 9 3

Allowable Peak Lilsear Heat Rate vs. Burnup 10 4 Excore Monitoring of LHR 11 5 DNB Monitoring 12 -

6 F xy , FpT and Core Power Limitations 13 5

d FC/TDB R1 l

- - - _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ . - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ _ _ _ _ _ _ - - _ _ - - _ _ _ _ _ _ _ - _ _ - _ . _- _A

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 3 OF 13 LJST Oy_T_AE_L_E Table No. Title Pace 1 TM/LP Coefficients c 2 Maximun F a and F xy Limits 7 FC/TDB R1 l

l

g _

^

q S'

. FORT CALHOUN STATION 1DB-VI

- TECHNICALJDATA BOOK- PAGE 5 OF 13 ,

CYCLE'14 CORE OPERATING-LIMITS REPORT

+ .

1.0 lHIB9DUCTIOH-

This report provides the cycle - specific limits for-

-operat, ion of the Fort Calhoun Station Unit 1 for Cycle--14 operation.- It includes limits for:-

1.1 TM/LD LSSS 4 Pump Operation (Pygp) 1.2 Core Inlet Temperature ~ (Tyg) 1.3 Power Dependent Insertion Limit (PDIL) 1.4 -Allowable Peak Linear Heat Rate 1.5 Excore Monitoring of LHR 1.6 Planar Radial Peaking Factor (FxyT) 1.7 Integrated Radial Peaking Factor (Fn) T cl.8 DNB Monitoring-1.9 FgT /F xy T versus Power Trada eff curve 1.10 Refueling Boron Concentration These-limits are appl'icable for the duration of Cycle 14.

For subsequent cycles the-limits will be reviewed and revised as necessary. In addition,_this report includes a number of cycle - specific-coefficients used in the fgeneration of_certain reactor protective system trip setpoints or allowable. increases _in radial peaking factors.

This report'has been prepared in accordance with the requirements of Technical Specification'5.9.S. The core operating limits have been developed _using the.NRC methodologies listed inLTechnical. Specification 5.9.5.b.

2.0 . CORE OPERATING LIMITS The-values and'11mits presented within this section have been derived using the NRC - approved methodologies' listed

in_ Technical Specification 5.9.5. All values'and limits.in-

-thisisection apply to Cycle 14 operation. Cycle,14 must be operated within the bounds of these limits and all others specified in the Technical Specifications.

FC/TDB. R1

FORT CALHOUN STATION TDB-VI .

TECHNICAL DATA BOOK PAGE 6 OF 13 3.0 IM/LP LIMIT The TM/LP coefficients for Cycle 14 are shown below:

Table 1 CoefR c.icAt Value a 29.73 S 18.44 y 1325 The TM/LP setpoint is calculated by the Pygg equation, shown __

below and in Figure 1:

P ygg = 2 9.73 PF (B) A1(Y) B + 18. 4 4T yp -11325 PF(B) = 1.0 B2100%

= -0.008B + 1.8 50% <B<100%

= 1.4 Bs50%

A1(Y) = -0.35294Y 2 + 1.08824 Y1 5 0.25

= 0.57143Y 3 + 0.875 Y3 > 0.25 Where:

B = High Auctioneered thermal (AT) or Nuclear Power, % of rated power Y = Axial Shape Index, asiu T z,; = Core Inlet Temperature, 'F P ygg = Reactor Coolant System Pressure, psia 4.0 MAXIMUM CORE INLET TEMPERATHE.E The maximum core inlet temperature (T73) for Cycle 14 shall not exceed 543*F.

This limit id not applicable during either a thermal power ramp 2 in excess of 5% of rated thermal power per minute or a thermal power step greater than 10% of rated thermal power.

5.0 POWER DEPENp_El[T INSERTION LIMIT The power dependent insertion limit is defined in Figure 2 for cycle 14 operation.

6.0 LINEAR REAT PATE The allowable peak linear heat rate vs. burnup is 14.2 kw/ft for!

Cycle 14 for all burnup points as shown on Figure 3.

FC/TDB R1

_ _q a

s FORT CALHOUN STATIOP TDB-VI TECHNICAL DATA BOOK FAGE 7 OF 13 )

1

- 7 .- O EXCORE MONITORING OF LHR 1 The allowable operation for power versus axial shape index for monitoring of LHR with excore detectors for Cycle 14 is shown in Figure 4.

8.o EEAKING FACTOR LIlilLS

-The maximum full power values for the unrodded planar radial peaking factor (FxyT ) and integrated radial peaking factor Fp) T are shown in Table 2.

Table 2 liaKimum F ' A1 Power F .__

g and F gy Limite Eeakina Factor Limits F xy T 1.85 F gT 1.79 9.0 DNB MONIJ'ORING The limits for DNB as a function of axial shape index and core power is shown in Figure 5.

Core-power shall be maintained within the limits established by the Better-Axial Shape Selection System (BASSS) for CEA insertion of the lead. bank of (65% (i.e., greater than or equal to '44.1- inches withdrawn) when BASSS is operable, or within the limits of Figure 5.

T

10. 0 Exyh_fg AND CORE POWER LIMJTATIONS Core power limitations'versus Fg T and F xy T are shown in Figure 6.

l 11.0 REFUEL.ING BORON CONCENTRATION-o -

The refueling boron concentration must be maintained with a boron concentration of_at least 1700_ ppm in the Reactor Coolant System to ensure a shutdown margin of not less than 5% with all CEAs withdrawn.

l l

t FC/TDB R1

FORT CALHOUN STATION TDB-VI-TECHNTCAL DATA BOOK PAGE 8 OF 13 590 ASI = -0.06 580 -

g ,

' LLI 570 -

$ ~

1 G: 560 \

\\

2400 psia

\-

l 2250 psia E 540

.$' s 2100 psia l

l- .O

^O 5 530 N -

g. .

Lu G: 520 L O \ 1750 psia O .

L l 510 -

l.

I 500 ' ' '

L

-60 70- 80 90 -100 110 120 o

l CORE POWER (% OF RATED)

L PVAR = 29.73PF(B)A1(Y)B + 18.44Ti n - 11325 PF(B) = 1.0 B 2.100%

= .008B + 1.8 50%< B<100%

= 1.4 - B & 50%

A1C() = -0.35294Y i + 1.08824 Yi 1.25

= 0.57143Yi + 0.875 Yi >.25 ni CYCLE 14. THERMAL MARGIN / LOW PRESSURE FIGURE COLR 4 PUMP OPERATION 1

=

. - - - ~ - .. .-

'.s

?-

l FORT.CALHOUN STATION TDB-VI' i TECHNICAL DATA BOO" PAGE 9 OF 13 I

- 126 1

100.8 LONG TERM STEADY S1 ATE .'~~~~

j

~ ~ '

' INSEPTION UMIT '/

/, [

0- *

(82.5)

- 75.6 . ,',

,' PPDil t.

126 - 50.4 l

SHORT TERM ',

'l l ry . INSERTION UM j

=$ - 100.8 - 25.2 l

-o '

l PDll or TRANSIENT 5 ,

INSERTION LIMIT

, s .E - 75.6 -0 D

l,

l .d- o ,

I L

g @ '-- 50.4 ,

EMERGENCY BORATION LIMIT

~'

G <

(12" BELOW PDil - REFER TO AOP-3)

(3 , , ,

_ $ 120 - 25.2 (25 2)

/

(13.2)

. u) ++ 100.8 - 0 O

c.

$ - 75.6 O

tc o

w l O O F - 50.4 b

- 25.2 ~ - 126 l

-0 - 100.8

[, - 75.6 o

O cr 0 - 50.4 l - 25.2 - )

V. a

-0 100 0 20 40 60 80  ;

REACTOR POWER (% OF ALLOWED POWER)

[. R1

/ CYCLE 14 FIGURE POWER DEPENDENT INSERTION LIMIT 2.

( ~COLR -

y JLAF29-1992 07 W FGOM ' -OFFD *%MFi TO g g7' p,g3 ,

L FORT CALHOUN STATION --- TDB-Vi PAGE 10 OF 13

}

• TECHNICAL DATA BOOK f

16 -

16 UNACCEPTABLE OPERATION i

m Z 14.2 KW/FT r-j 14 E . 1 ACCEPTABLE OPERATION

- I:

h 13 ..

1.

12 0 5000 10000 15000 20000 BURNUP(gwo/m o) L  :

1.

R1 CYCLE 14 ALLOWkBLE PEAK LINEAR HEAT RATE FIGURE CocR VS,BURNUP 3

e

. FORT CALHOUN STAT 20!3 TDBrVI l '

PAGE 11 0F 13

, TECHNICAL DATA BOOK I

110 100 CC W 90 t M r O ,, - ( .06, 80)

'~

( 1,80)

D 80 W

CC O 70 ( .2,70) (.2,70)

O W 60 3

O d EO 40 t- -

i wsd a

W 30 O

tr W

D. 20 1

10 0 i 4 2 0 .2 .4 AXIAL SHAPE INDEX (ASIU) 31 CYCLE 14 EXCORE MONITORING OF LHR

______________.__._______m____________._____________________________._ mm _

FORT CAUiOUN STATION TDB-VI- ,

TECHNICAL DATA BOOK PAGE 12 OF 13 110 02 s 100) (.1.100) 100 {

90

/ t oc [i W \

$ 8o

( )

l O  ;

n. / ,

y 70 -

CC I O < 1s,so)

.is,so)

O 60

.a W

g 50 0

._t J 40 4 '

g O 30 W

Z W. 20-O W

W

n. 10 0

4 .2 0 .2 .4

- AXIAL SHAPE INDEX (ASlU) .

NOTE: WHEN BASSS IS OPERABLE THIS FIGURE IS SUPERSCEDED BY THE BASSS DNB ALLOW-ABLE POWER VALUE R1a CYCLE 14 DNB' MONITORING COLR 5

F ,,

• l ' FORT CALHOUN STATION TDB-VI TECilNICAL DATA DOOK PAGE 13 OF 13 1

110 T T Fr Fxy i LIMIT LIMIT 100 ,

W W 90 (1.79,90) (1.85,90)

O s E 80 W

W h 70 (1.93.75) (2.01. 75)  :

O W

g 60 0

J

.J 50 4  ;

LL O 4o H

Z W

g 30 C i W

1 20 10 0

F 1.75 1.80 1.85 1.90 1.95 2.00 2.05 Fxy T

and Fr7 i R1 1 -

CYCLE 14 p T, p,T, AND CORE POWER LIMITATIONS FIGURE L-COLR_

m 6-l-

w w w a- owrs wwv-n'-'rm~ ~ -+**+=-c*'- '

Meev<<~-- -*er--usee-w, -mwr---'- =< <v e 9 m- ' w > '=Mo' ~ m -r-g v t'79-