ML20107H628

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Corrected Rev 9 to Core Operating Limit Rept, Adding Figure to COLR for Axial Power Distribution LSS for 4 Pump Operation
ML20107H628
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Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 10/06/1995
From: Weber W
OMAHA PUBLIC POWER DISTRICT
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NUDOCS 9604240186
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Text

_ _ _ _ _ - - _ . _

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

Title:

CORE OPERATING LIMIT REPORT W

3 FC-68 Number: 47372 Reason for Change: Add figure to COLR for " Axial Power-Distribution LSSS for 4 Pump Operation".

Contact Person: William O. Weber Documentable Error (a) : Page 16 i

ISSUED: 10-06-95 4:00 pm R9 kk

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, FORT CALHOUN STATION TDB-Vi

. TECHNICAL DATA BOOK PROCEDURE PAGE 10F 16 i .

e i

J Fort Calhoun Station, Unit 1 i

, Cvele 16 Core Onoratina Limits Renort e

1 i

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

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FORT CALHOUN STATION TDB-VI

, TECHNICAL DATA BOOK PROCEDURE PAGE 2 CF 16 TABLE OF CONTENTS i

llem Descriotion EaQR 1.0 Introduction 5 2.0 Core Operating Umits 5

3.0 TM/LP Umit 6 4.0 Maximum Core inlet Temperatute 6 5.0 Power Dependent insertion Umit 7 6.0 Unear Heat Rate 7

~

-7.0 Excore Monitoring of UiR 7 8.0 Peaking Factor (FaT, p,yT) Umits 7 9.0 DNB Monitoring 7 10.0 FRT, FxyT and Core Power Umitations 8 11.0 Refueling Boron Concentration 8 12.0 Axial Power Distribution 8 l )

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FORT CALHOUN STATION TDB-VI cTECHNICAL DATA BOOK PROCEDURE PAGE 3 OF 16 LIST OF TABLES 1

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Table No. Iitig g 1

1 TM/LP Coefficients 6 i 2 Maximum Fa and Fxy Umits 7 I

f h

l l

1 1

4- ,

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. - - _ =-

FORT CALHOUN STATION TDB-VI

. TECHNICAL DATA BOOK PROCEDURE PAGE 4 OF 16 LIST OF FIGURES Fiaure No. M EaQR 1 Thermal Margin / Low Pressure 4 Pump Operation 9 2 Power Dependent Insertion Umit 10 3 Allowable Peak Unear Heat Rate vs. Bumup 11 4 Excore Monitoring of LHR 12 5 DNB Monitoring 13 6 BASSS Allowable Power 14

! 7 FsT, Fxy7 and Core Power Limitations 15 8 Axial Power Distribution LSSS for 4 Pump Operation 16 i

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4 R9

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, FORT CALHOUN STATION TDB-VI

. TECHNICAL DATA BOOK PROCEDURE PAGE 5 OF 16 Cvels 16 Core Onoratina Limits Renort 1.0 introduction This report provides the cycle-specific limits for operation of the Fort Calhoun Station Unit 1 for Cycle 16 operation. It includes limits for:

1.) TM/LP LSSS 4 Pump Operation (PVAR) 2.) Core inlet Temperature (TIN) 3.) Power Dependent insertion Umit (PDIL) '

4.) Allowable Peak Unear Heat Rate 5.) Excore Monitoring of LHR ~ 1 T '

6.) Planar Radial Peaking Factor (Fxy ) T 7.) Integrated Radial Peaking Factor (Fn )

8.) DNB Monitoring T T 9.) Fn /Fxy versus Power Trade off curve 10.) Refueling Boron Concentration 11.) Axial Power Distribution l These limits are applicable for the duration of Cycle 16. For subsequent cycles the limits will be l

reviewed and revised as necessary, in addition, this report includes a number of cycle-specific  !

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

2.0 Core Operating 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 denved 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. (TAC No. M85845)

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 6 OF 16 l 3.0 TMILP Limit The TM/LP coefficients for Cycle 16 are shown below:

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

PvAR = 29.73 PF(B) A1(Y)B + 18.44 TIN - 11470 PF(B) = 1.0 B2.100%

= -0.0088 + 1.8 50% < B < 100%

= 1.4 B A 50%

A1(Y) = -0.3529Yi + 1.0882 Yi 5 0.25

= 0.5714Yi + 0.857 Y > 0.25 3

, Where:

B = High Auctioneered thermal (AT) or Nuclear Power, % of rated power Y = Axial Shape index, asiu Ts i = Core inle: Temperature, CF PVAR = Reactor Coolant System Pressure, psia 4.0 Maximum Core inlet Temnerature The maximum core inlet temperature (Ti s) 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 16 5.0 Power Decondent insertion Limit The power dependent insertion limit is defined in Figure 2 for Cycle 16 operation.

6.0 Linear Heat Rate The allowable peak linear heat rate vs. burnup for Cycle 16 is 15.5 kW/ft. The allowable peak linear heat rate for Cycle 16 is shown in Figure 3.

7.0 Excore Monitorina of LHR The allowable operation for power versus axial shape index for monitoring of LHR with excore

, detectors for Cycle 16 is shown in Figure 4.

l 8.0 Egakina Factor Limits The Cycle 16 maximum full power values for the unrodded planar radial peaking factor (FyT) and integrated radial peaking factor (FnT) are shown in Table 2.

Table 2 Mavimum Full Power Fn and 3F Limits Etakina Factor Limitt FnT 1.77 FT9 1.86 1

l l

9.0 DNB Monitoring 1

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 seperate LOCA and fuel performance limits to be maintained by the operators while operating with BASSS.

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FORT CALHOUN STATION TDB-VI

. TECHNICAL DATA BOOK PROCEDURE PAGE 8 OF 16 10.0 F,T, p T and Core Power Limitations Core power limitations versus Fif and FxyTare snown in Figure 7 for Cycle 16.

4 11.0 Refuelina Baron 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.

12.0 Axlal Power Distribution l

The axial power trip is provided to ensure that excessive axial peaking will not cause fuel damage. l The Axial Shape index is determined from the axially split excore detectors. The set point functions, I

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shown in Figure 8 ensure that neither a DNBR of less than 1.18 nor a maximum linear heat rate of more than 22 kW/ft (deposited in the fuel) will exist as a consequence of axial power maldistributions. Allowances have been made for instrumentation inaccuracies and uncertainties l associated with the excore symmetric offset - incore axial peaking relationship.

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i FORT CALHOUN S1ATION TDB-VI '

, TECHNICAL DATA BOOK PROCEDURE PAGE 9 OF 16 590

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l ASI = -0.06 580 ' '

lL LAI 570 E N l 12: 560 \ 'N L1J Q.

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.I 2250 psia h 550 ' ' '

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\I 2100 psia E 540

>=

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5 o 530 g

C '

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1750 psia 12: 520 0

0 -

510 1

500 '

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

. l PvAR = 29.73PF(B)A1(Y)B + 18.44Ti s - 11470 PF(B) = 1.0 B 2.100%

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

= 1.4 B $ 50%

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

= 0.5714Yi + 0.857 Yi >.25 CYCLE 16 THERMAL MARGIN / LOW PRESSURE FIGURE COLR 4 PUMP OPERATION 1 R9

' FORT CA' HOUN STATION TDB-VI

. TECHNICAL DATA BOOK PROCEDURE PAGE 10 OF 16

- 126

- 100.8 LC NG T1ERM SfTEADY STATE ,

INBERTION UMIT ,

o - 75.6 l ,

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- 126 - 50.4 INSERTIOPl UM{, '

5 - 100.8 - 25.2 i .

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$ I , PDIL or TRANSIE.NT h *

!,, ',/, INS $RTION UMIT 3 [ - 75.6 -0 i r g o ,l' , '

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EMERC,ENCY BORATION LIMIT (35.2)

,-'/ (12" HELOVf PDlL - RE :ER TO AOF -3)

- 25.2 - 126 (25.2)

- 100.8 l

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$ - 50.4

- 25.2 4

-0 0 20 40 60 80 100 i

REACTOR POWER (% OF ALLOWED POWER) i 4

CYCLE 16 FIGURE POWER DEPENDENT INSERTION LIMIT COLR 2 R9

FORT CALHOUN STATION TDB-VI

, TECHNICAL DATA BOOK PROCEDURE PAGE 11 OF 16 18 l

j UNACCEPTABLE OPERATION 16  ; ,

15.5 KW/FT

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) ACCEPTABLE OPERATION 12 l 2 '

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BURNUP (MWD /MTU) 1 CYCLE 16 ALLOWABLE PEAK LINEAR HEAT RATE FIGURE L COLR VS.BURNUP 3 R9

FORT CALHOUN STATION TDB-VI

, TECHNICAL DATA BOOK PROCEDURE PAGE 12 OF 16

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j AXIAL SHAPE INDEX (ASIU)

CYCLE 16 FIGURE COLR EXCORE MONITORING OF LHR 4

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FORT CALHOUN STATION TDB-V:

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, ECHNICAL DATA BOOK PROCEDURE PAGE 13 OF 16 110 ,

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WHEN BASSS IS OPERABLE THIS FIGURE IS

! SUPERSCEDED BY FIGURE 6 - BASSS DNB ALLOWABLE POWER CYCLE 16 FIGURE i COLR DNB MONITORING 4

5 99 l

FORT CALHOUN STATION TOB-VI

, TECHNICAL DATA BOOK PROCEDURE PAGE 14 OF 16 110 ,

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, . FORT CALHOUN STATION TDB-VI

. TECHNICAL DATA BOOK PROCEDURE PAGE 15 OF 16 110 ,

I i FnT g,yT I 100 i (1.86,90)

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CYCLE 16 FIGURE I

COLR FRT, p,yT, and Core Power Limitations 7

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, . FORT CALHOUN STATION TDB-VI

. TECHNICAL DATA BOOK PROCEDURE PAGE 16 OF 16 j

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AXIAL SHAPE INDEX (ASIU) 1 CYCLE 16 Axial Power Distribution LSSS FIGURE

! COLR for 4 Pump Operation 8 R9 A

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