ML20135A654

Rev 11 to COLR, Updating COLR Figures 4,5,6,7A & 8 to Reflect New LCO & LSSS

ML20135A654
Person / Time
Site:	Fort Calhoun
Issue date:	08/27/1996
From:	Guinn M OMAHA PUBLIC POWER DISTRICT
To:
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ML20135A648	List: ML20135A645 ML20135A654 ML20135A658
References
NUDOCS 9612030333
Download: ML20135A654 (19)

Text

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Fort Calhoun Station Unit No.1 TDB-VI TECHNICAL DATA BOOK

Title:

CORE OPERATING LIMIT REPORT FC-68 Number: 48123 Reason for Change: Update Colr Figures 4,5,6,7A, and 8 to reflect new LCO, LSSS, and setpoint requirements as a result of widening the ASI tent from middle-of-cycle to end-of-cycle 16 operations.  ;

l Contact Person: Marcus J. Guinn l l

lSSUED: 08-27-96 4:00 pm R11 9612030333 961125 DR ADOCK 05 g5

FORT CALHOUN STATION TDB-VI '

. TECHNICAL DATA BOOK PROCEDURE PAGE 1 OF 17 I

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Fort Calhoun Station, Unit 1 Cycle 16 Core Operatina Limits Report l

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Due to the critical aspects of the safety analysis inputs contained in this report, changes may l not be made to this report without concurrence of the Production Engineering Division, i Nuclear Engineering Department. I i

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FORT CA1.HOUN STATION TDB-VI ~

. TECHNICAL DATA BOOK PROCEDURE PAGE 2 OF 17 TABLE OF CONTENTS 11gm Descriotion Eage ,

1.0 Introduction 5 l 20 Core Operating Umits 5 3.0 TM/LP Umit 6 l 4.0 Maximum Core Inlet Temperature 6 l 5.0 _ Power Dependent insertion Umit 7 6.0 Unear Heat Rate , 7  !

7.0 Excore Monitoring of LHR 7 8.0 Peaking Factor (FRT, pmT) Umits 7 9.0 - DNB Monitoring 7 l

.10.0 FaT, E T and Core Power Umitations 8- l m

Refuehng Boron Concentration 11.0 8 i 12.0 Axial Power Distribution 8 l I 1

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FORT CALHOUN STATION TDB-VI '

. TECHNICAL DATA BOOK PROCEDURE PAGE 3 OF 17 LIST OFTABLES Table No. Ijtjg g 1 TM/LP Coefficients 6

.2 Maximum Fa and F n Umits 7 9

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. FORT CALHOUN STATION TDB-Vi ~

. TECHNICAL DATA BOOK PROCEDURE PAGE 4 OF 17 LIST OF FIGURES Fiaure No. IllLG EaQA 1 Thermal Margin / Low Pressure 4 Pump Operation 9 2 Power Dependent insertion Limit 10 3 Allowable Peak Linear Heat Rate )

vs. Burnup 11 4 Excore Monitoring of LHR 12 5 DNB Monitoring 13 6 BASSS Allowable Power 14 ,

7 FnT, FxyT and Core Power Umitations 15 i 7A FaT, FxyT and Core Power Limitations When ICI System is Inoperable 16 8 Axial Power Distribution LSSS for 4 Pump Operation 17 1

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l FORT CALHOUN STATION TDB-VI '

. TECHNICAL DATA BOOK PROCEDURE PAGE 5 OF 17 l

Cycle 16 Core Operatlag Limits Report l l

l 1.0 Introduction j This report provides the cycle-specific limits for operation of the Fort Calhoun Station Unit 1 for J

Cycle 16 operation. It includes limits for: 1 1.) TM/LP LSSS 4 Pump Operation (PVAR) 2.) Core InletTemperature (TIN) 3.) Power Dependent insertion Limit (PDIL) 4.) Allowable Peak Unear Heat Rate 5.) Excore Monitoring of LHR 6.) Planar Radial Peaking Factor (FxyT) 7.) Integrated Radial Peaking Factor (FRT) 8.) DNB Monitoring l T T  !

9.) F R/Fxy versus Power Trade off curve 10.) Refueling Boron Concentration l 11.) Axlal Power Distribution These limits are applicable for the duration of Cycle 16. For subsequent cycles the limits will be reviewed and revised as necessary. In addition, this report includes a number of cycle-specific i i

coefficients used in the generation of certain reactor protective system trip setpoints or allowable Increases in radial peaking factors.  ;

2.0 . Core Ooeratina Limits All values and limits in this TDB section apply to Cycle 16 operation. Cycle 16 must be operated within the bounds of these limits and all others specified in the Technical Specifications. This report has been prepared in accordance with the requirements of Technical Specification 5.9.5. The -

values and limits presented within this TDB section have been derived using the NRC approved methodologies listed below:

OPPD-NA-8301, " Reload Core Analysis Methodology Overview" Rev. 6, dated December 1994. (TAC No. M89455)

OPPD-NA-8302," Reload-Core Analysis Methodology, Neutronics Design Methods and Verification" Rev. 4, dated December 1994. (TAC No. M89456)

OPPD-NA-8303, " Reload Core Analysis Methodology, Transient and Accident Methods and Verification", Rev. 04, dated January 1993. (l'AC No. M85845)

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FORT CALHOUN STATION TDB-VI '

. TECHNICAL DATA BOOK PROCEDURE PAGE 6 OF 17 3.0 TM/LP Limit The TM/LP coefficients for Cycle 16 are shown below:

Tahle 1 Coefficient Value a 29.73 p 18.44 y - 11470 The TM/LP setpoint is calculated by the PVAR equation, shown below and in Figure 1:

PVAR = 29.73 PF(B) A1(Y)B + 18.44Ti s - 11470 PF(B) = 1.0 B A 100%

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

= 1.4 B $ 50%

A1(Y) = -0.3529Yi + 1.0882 Y s 0.25 i

= 0.5714Yi + 0.857 Yi > 0.25 Where: l B = High Auctioneered thermal (AT) or Nuclear Power, % of rated power Y = Axlal Shape Index, aslu Tn i = Core inlet Temperature, F '

PVAR = Reactor Coolant System Pressure, psia  ;

4 4.0 Maximum Core inlet Temperalyta The maximum core inlet temperature (f in) for Cycle 16 shall not exceed 545'F.

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

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FORT CALHOUN STATION TDB-VI

. TECHNICAL DATA BOOK PROCEDURE PAGE 7 OF 17 1

5.0 ED.E9LD_tRED. d ent insertion Limit The power dependent insertion limit is defined in Figure 2 for Cycle 16 operation.

.I 6.0 Linear Heat Rata

) ,

i The allowable peak linear heat rate vs. burnup for Cycle 161s 15.5 kW/ft. The allowable peak linear f heat rate for Cycle 16 is shown in Figure 3. l 7.0 Excore Monitoring of LHR I

The allowable operation for power versus axial shape index for monitoring of LHR with excore detectors for Cycle 16 is shown in Figure 4.

8.0 Peakina Factor Limits T

The Cycle 16 maximum full power values for the unrodded planar radial peaking factor (Fn)and f T

integrated radial peaking factor (Fa ) are shown in Table 2.  :

Table 2 Maximum Full Power Fo and 3 F Limits Egaking Factet Limits T 1.77 Fa FnT 1.86 -

9.0 DNB Monitoring The Cycle 16 limits for DNB as a function of axial shape index and core power is shown in Figure 5.

When the Better Axial Shape Selection System is operable, during Cycle 16, the core power is limited as a function of the axial shape index as shown in Figure 6. Figure 6 will eliminate the need for separate LOCA and fuel performance limits to be maintained by the operators while operating with BASSS.

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._q FORT CALHOUN STATION TDB-VI

. TECHNICAL DATA BOOK PROCEDURE PAGE 8 OF 17 -

l 10.0 FoT. FyT and Core Power Limitations T

Core powerlimitations versus F TR and Fxy are shownin Figure 7 for Cycle 16. If the ICI System is declared inoperable, Figure 7 will be superceded by Figure 7A.

11.0 Refuelina Boron Concentration The refueling boron concentration must be maintained with a boron concentration of at least 2000 ppm in the reactor coolant system to ensure a shutdown margin of not less than 5% with all CEAs withdrawn.

i 12.0 Axial Power Distribution The axial power trip is provided to ensure that excessive axial peaking will not cause fuel damage. l The Axlal Shape Index is determined from the axially split excore detectors. The setpoint functions, I shown in Figure 8 ensure that neither a DNBR of less than 1.18 nor a maximum linear heat rate i of more than 22 kW/ft (deposited in the fuel) will exist as a consequence of axial power l maldistributions. Allowances have been made forinstrumentation inaccuracies and uncertainties '

associated with the excore symmetric offset - Incore axlal peaking relationship.

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FORT CALHOUN STATION TDB-VI

. TECHNICAL DATA BOOK PROCEDURE PAGE 9 OF 17 590 ASl = -0.06 580 -

g 3

uJ 570 \ .

(I" 2400 psia 560

~

2250 psia 2100 psia i

- 540 x g Z -

5 530 o g O \

U -

1750 psia gr: 520 0

0 -

510 500 ' ' ' ' '

60 70 80 90 100 110 120 CORE POWER (% OF RATED)

PVAR = 29.73PF(B)A1(Y)B + 18.44Ti n - 11470 PF(B) = 1.0 By_100%

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

= 1.4 B s50%

l A1(Y) = -0.3529Yi + 1.0882 Yi 5 25 l

= 0.5714Yi + 0.857 Yi >.25 I CYCLE 16 THERMAL MARGIN / LOW PRESSURE FIGURE l COLR 4 PUMP OPERATION 1  !

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. TECHNICAL DATA BOOK PROCEDURE PAGE 10 0F 17

- 126

'~~~~

- 100.8 ' I )

Lc.NGTlERM STEAD" STAl E ,

' (

[

3 l IN SERTION LilAIT f

/ (82.5)

o - 75.6 l ,

o I ,

- 126 - 50.4 -

INSERTIO!4 LIMi{,,"

. 5 - 100.8 - 25.2 l .

U ' # , PDIL or TRANS!E NT

, -, /, INSE.RTIOrl LIMI r E -0 -

2- 75.6 ,

W 8 ,'/,,

. z e ,

y 0 - 50.4 ,

EMERC ENCY BORATION LIMIT

- 25.2 (35.2)

- 126 (2s.2)'

'/[ (12"IIELOVf PDil - RE :ER TO AOF -3) 4 t- -0 - 100.8 m

O

n.

[ - 75.6 Q

O 5 m x

! O O - 50.4 m

U - 126 - 25.2

- 100.8 - 0

- 75.6 S

8 0 - 50.4 l

- 25.2 2

i -0 1

0 20 40 60 80 100 REACTOR POWER (% OF ALLOWED POWER) i FIGURE CYCLE 16 POWER DEPENDENT INSERTION LIMIT COLR 2 R11

FORT CALHOUN STATION TDB-VI ~

. TECHNICAL DATA BOOK PROCEDURE PAGE 11 OF17 18 UNACCEPTABLE OPERATION 16 15.5 KW/FT 14 i

ACCEPTABLE OPERATION 12

.t.

h 10 kE 8

i m ,

I l E

b i z <

]

4  !

0 0 5000 10000 15000 20000 BURNUP (MWD /MTU)

CYCLE 16 ALLOWABLE PEAK LINEAR HEAT RATE FIGURE COLR VS.BURNUP 3 R11

FORT CALHOUN STATION TDB-VI

. TECHNICAL DATA BOOK PROCEDURE PAGE 12 OF 17 l NOTE

Rodded operation is prohibited above 90% of Rated Thermal Power l l

110 i

100 (-n 12,1 m) 90 ( --GA4d 14;90)

W

* / \

O 80 (_2.23,33 (,,zo,,3, I b i LM E 7o / k O' i

O '

i O W 60 g

b '

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J 50 /[ l k l

! 4

u O 4o ;_c,3,43) (3;3;43)

, z

W

! O 30

E i W

o.

', 20 10 0

- 0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 AXIAL SHAPE INDEX (ASIU)

EXCORE MONITORING OF LHR CO R 4 R11

FORT CALHOUN STATION TDB-VI

. TECHNICAL DATA BOOK PROCEDURE PAGE 13 OF 17 110 100 [-0_12 1004 (0=1 (10@

E W

g 90 g 2

g 80 / \

K O '

Q 70 O .

W g 60

/

O \

J J 50

\ '

<C

u. ,

O 40 (-0 5,40) (0.ii,40)-

Z W

O * .

E W

0- 20 10 i

0

- 0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 AXIAL SHAPE INDEX (ASIU)

NOTE: WHEN BASSS IS OPERABLE THIS FIGURE IS SUPERCEDED BY FIGURE 6 - BASSS DNB ALLOWABLE POWER 6 '

COLR DNB MONITORING 5 R11

! j 'i ,  !!- 'l!i, l :j  !

C TF CY EO OC L CR HT L E R 0WEgWZ On 4dJogWO Q

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. N I C CA 1

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0 2

0 3

0 0 4 5 0

6 0

7 0

8 0 0 0

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FORTCALHOUN STATION TDB-VI ~

. TECHNICAL DATA BOOK PROCEDURE PAGE 15 OF 17  !

110 p

l FnT *7 100 l

(1.86,9Q g 90 W N N l 3 (1 77,90)

N N

O 80 N w CL i W -

\,75) (2.oss,7sf E 70

. O

O

! O 60 i W l 3 l O 50

J J

<C  !

u, 40  !

O '

l F 30 l z ,

W

' O E 20 i Lu (1.

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! 10 0

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1.75 1.80 1.85 1.90 1.95 2.00 2.05 2.10 1

i PEAKING FACTOR l

i I CYCLE 16 FIGURE I COLR FnT, FxyT , and Core Power Limitations 7 R11 i

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! TECHNICAL DATA BOOK PROCEDURE PAGE 16 OF 17 i

l NOTE: Rodded operation is prohibited above 90% of Rated Thermal Power l l 110 T T l Fn F xy

100 1

g (1.86,9 0 l 90 i W N f g (1.77,90) l O 80 x N( .92, 80)

D. N ~%

! W

\

(1.9.29,7 5)

N (2.055,75; l

g

! O i O

! O 60 -

l W i 3 ,

i O 50  !

i J J

i 4

i u. 40 l

a O

i H 30

! Z 4 W

! O E 20

'. W E

a j 10 i

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2.10 1.75 1.80 1.85 1.90 1.95 2.00 2.05 PEAKING FACTOR CYCLE 16 FaT, F T, and Core Power Limitations FIGURE COLR When$he ICI System is Inoperable 7A R11

FORT CALHOUN STATION TDB-VI

, TECHNICAL DATA BOOK PROCEDURE PAGE 17 OF 17 -

4 120 ,

, 1 J  !

l (0,1,12) i 110 A

/\

100 I- 0Ib #0 I6'I00 E l0 [ 3

! i 90 g

/ \

Q 3

! O=

2

' W 80 (0.4,!;o) (0.4,!!o) g O

O O 70 l \

! W f T N k i O 60

._J J 1

! 4 50 -

(-u.u,: iuj 4

g p---.u,:,u) l O

l-g 40 4

W i O l l

E 30 W

O.

20 i

10 i

-0.8 -0.s -0.4 -0.2 0.0 0.2 0.4 0.6 0.8 l

! AXIAL SHAPE INDEX (ASIU)

CYCLE 16 Axial Power Distribution LSSS FIGURE COLR for 4 Pump Operation 8 R11

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, Attachment 2 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION UNIT NO. 1 l l

CORE OPERATING LIMITS REPORT (COLR)

REVISION 12 l

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