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 and F Limits 7

g xy 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

T T

8.0 Peaking Factor (F Fg) Limits 7

xy,

9.0 D!lB-Monitoring 7

10.0.

F T, p T and Core Power Limitations 7

g x

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 T

6 F

F and Core Power Limitations 13 xy,

p 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 and F Limits 7

a xy 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 T

1.6 Planar Radial Peaking Factor (Fxy )

T 1.7 Integrated Radial Peaking Factor (Fn) cl.8 DNB Monitoring-T T

1.9 Fg /F versus Power Trada eff curve xy 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 P equation, shown ygg below and in Figure 1:

P

= 2 9.73 PF (B) A1(Y) B + 18. 4 4T

-11325 ygg yp 1.0 B2100%

PF(B)

=

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

1.4 Bs50%

=

A1(Y) = -0.35294Y

+ 1.08824 Y

5 0.25 2

1

= 0.57143Y

+ 0.875 Y

> 0.25 3

3 Where:

B

= High Auctioneered thermal (AT) or Nuclear Power, % of rated power Y

= Axial Shape Index, asiu T,;

= Core Inlet Temperature,

'F z

P

= Reactor Coolant System Pressure, psia ygg 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

)

- 7.- O EXCORE MONITORING OF LHR 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 T

T peaking factor (Fxy ) and integrated radial peaking factor Fp) are shown in Table 2.

Table 2 liaKimum F ' A1 Power F.__ and F Limite g

gy Eeakina Factor Limits T

F 1.85 xy T

F 1.79 g

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.

10. 0 Exyh_fg AND CORE POWER LIMJTATIONS T

T T

Core power limitations'versus F and F are shown in g

xy Figure 6.

11.0 REFUEL.ING BORON CONCENTRATION-l 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

5 N

l-

.O 530

^O 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 + 18.44T n - 11325 i

PF(B)

= 1.0 B 2.100%

=

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

= 1.4

- B & 50%

A1C()

= -0.35294Y + 1.08824 Y 1.25 i

i

= 0.57143Y + 0.875 Y >.25 i

i 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

.'~~~~

j 100.8 LONG TERM STEADY S1 ATE

~

~

INSEPTION UMIT

'/

/, [

0-(82.5)

- 75.6 PPDil

'l l

SHORT TERM t.

126

- 50.4 INSERTION UM j

l ry

=$

- 100.8 - 25.2 l

-o 5

l PDll or TRANSIENT s

.E - 75.6

-0 l,

INSERTION LIMIT D

l

.d-o L

I EMERGENCY BORATION LIMIT

'-- 50.4 g

~'

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

G (3,,

120

- 25.2 (25 2)

/

_ (13.2) u)

++ 100.8 - 0 O

c.

- 75.6 O

o tc w

O - 50.4 l

O F

b

- 25.2 ~

- 126 l

-0

- 100.8

[, - 75.6 oO cr0 - 50.4 l

- 25.2 -

)

V.

a

-0 0

20 40 60 80 100 REACTOR POWER (% OF ALLOWED POWER)

[.

R1 FIGURE

/

CYCLE 14 POWER DEPENDENT INSERTION LIMIT 2.

(

~COLR

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

L TDB-Vi

}

FORT CALHOUN STATION ---

TECHNICAL DATA BOOK PAGE 10 OF 13 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 ALLOWkBLE PEAK LINEAR HEAT RATE CYCLE 14 FIGURE CocR VS,BURNUP 3

e FORT CALHOUN STAT 20!3 TDBrVI l

TECHNICAL DATA BOOK PAGE 11 0F 13 I

110 100 CCW 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 a

w sd 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

{/

t

[i 90 oc W

\\

8o

(

)

O n.

/

y 70 CC I

O 1s,so)

.is,so)

O 60

.a Wg 50 0

._t J

40 4

g O

30 WZ W.

20-OW 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 5

COLR

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 WW h

70 (1.93.75)

(2.01. 75)

O W

60 g

0J

.J 50 4

LL O

4o HZ Wg 30 C

i W

1 20 10 0

F 1.75 1.80 1.85 1.90 1.95 2.00 2.05 T

7 Fxy and Fr i

R1 1 -

CYCLE 14 p

T, p,T, AND CORE POWER LIMITATIONS FIGURE L-m l-COLR_

6-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-

'