ML20236Q996

Reload Safety Evaluation,Catawba Nuclear Station Unit 2 Cycle 2

ML20236Q996
Person / Time
Site:	Catawba
Issue date:	09/30/1987
From:	Dzenis E DUKE POWER CO.
To:
Shared Package
ML20236Q968	List: ML20236Q965 ML20236Q969 ML20236Q996
References
NUDOCS 8711230013
Download: ML20236Q996 (52)

Text

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l RELOAD SAFETY EVALUATION  ;

CATAWBA NUCLEAR STATION .

UNIT 2 CYCLE 2-1 l September, 1987 i

Edited by: C.-R. Savage l l

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Approved: h E. A.-.Dzenis, Manager 9 Core Operations-Nuclear Fuel Division i

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l TABLE 0F~ CONTENTS i

Title -Page- .

1

1.0 INTRODUCTION

AND

SUMMARY

1-1.1 - INTRODUCTION ' 1' 1.2 GENERAL DESCRIPTION l-1.3 .' CONCLUSIONS. '2-1 2.0 REACTOR DESIGN ,

-3 .

I 2.1 MECHANICAL DESIGN 3 h 2.2 NUCLEAR DESIGN .4 2.3 THERMAL AND HYDRAULIC DESIGN 5 3.0 POWER CAPABILITY AND' ACCIDENT EVALUATION 6' 3.1 POWER CAPABILITY 6 3.2 ACCIDENT EVALUATION- 6 3.2.1 KINETIC PARAMETERS 7-3.2.2 . CONTROL R0D WORTHS 7 3.2.3 CORE PEAKING FACTORS 7 _.

1 4.0 TECHNICAL SPECIFICATION CHANGES 8  ;

5.0- REFERENCES 9 l APPENDIX A - ItCHNICAL SPECIFICATION PAGE CHANGES. j 7m .. 70..

3

-4 LIST 0F TABLES Table Title- Page 1 FUEL ASSEMBLY DESIGN PARAMETERS :10 2 . KINETIC CHARACTERISTICS- 11 3 END-OF-CYCLE SHUTDOWN REQUIREMENTS AND MARGINS 12 4 CONTROL ROD EJECTION ACCIDENT PARAMETERS 13

. LIST OF FIGURES Figure Title Page . -

1 CORE LOADING PATTERN 14-

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1.0 INTRODUCTION

AND

SUMMARY

1.1. INTRODUCTION This report presents an evaluation for Catawba Unit 2, Cycle 2, which demonstrates that the core reload will not adversely affect the safety of the plant. This evaluation was performed utilizing the methodology described in WCAP-9273-A, " Westinghouse Reload Safety Evaluation Methodology"(II.

All of the accidents comprising the licensing bases (2) which could potentially be affected by the fuel reload have been reviewed for the Cycle 2 design described herein, with the exception of the Boret Dilution Event for I operation in Modes 3 thru 6 which will be addressed by Duke Power Company for Cycle'2. The results.of new analyses and the justification for the f

l applicability of previous analyses are included in safety evaluations for the l

RTD Bypass' Elimination (13) , the VH1 Elimination (14) , the Low-T avg Setpoint Modification (15) , and in this evaluation.

1.2 GENERAL DESCRIPTION The Catawba Unit 2, Cycle 2 reactor core contains 193 Optimized Fuel Assemblies arranged in the core loading pattern configuration shown in Figure-

1. During t'e n Cycle 1/2 refueling,- 64 Region 1 fuel assemblies'will t^e replaced with 64 Region 4 fuel assemblies. A summary of the Cycle 2 fuel inventory is given in Table 1.

Nominal core design parameters utilized for Cycle 2 are as follows:

Core Power (MWt) 3411 System Pressure (psia) 2250 Core Inlet Temperature ('F) 561.3 Thermal-Design Flow (gpm) 373,200*

' Average Linear Power Density (kw/ft) 5.43 (based on 144" active fuel length) l

• The current licensing basis LOCA analyses have a Thermal Design flow of' 387,600 gpm while the UHI Removal LOCA analyses used a Thermal Design Flow value of. 377,000 gpm.

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1.3 CONCLUSION

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From the evaluation presented in this report, it is concluded that the Cycle 2 design does not cause the previously acceptable safety. limits to be exceeded.

This conclusion is based on the following: .

1. Cycle 1 burnup.is'between 13,500 and 15,250 MWD /MTU. ]

1

2. ' Cycle 2 burnup is. limited to a maximum of.12,000 MWD /MTU which includes"a coastdown.

- 3. .There is adherence to all plant operating limitations in the Technical Specifications including those changes presented.in Section 4.0 of--this 1

report. 1 i

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2.0 REACTOR DESIGN 2.1 NECHANICAL DESIGN The Region 4 fuel assemblies are Westinghouse Optimized Fuel Assemblies (OFAs)'

which have a smaller rod p'lenum spring than that used in Regions 1, 2, and 3.

This new spring design satisfies a change in the non-operational 6g loading design criterion to "4g axial and 6g lateral loading with dimensional stability." Notification of Westinghouse's plans to generically incorporate this criterion change and the justification of no unreviewed safety questions were previously transmitted to the NRC via Reference 3. The reduced spring l force reduces the potential for pellet chipping in the fuel rod.

i

The Cycle 2 reload contains fuel rods using a reduced length chamfered pellet in the Region 4 fuel. This standardized pellet design maintains the same nominal UO 1 ading per assembly which the non-chamfered pellets contained 2

in previous fuel Regions 1 and 3 for Catawba Unit 2. This pellet chamfer will reduce pellet chipping during manufacturing and handling.

The Region 4 assemblies utilize the Reconstitutable Top Nozzle (RTN) in ]

l conjunction with long tapered bottom end plugs in the fuel rods to allow for i l easy removal and reinsertion of individual fuel rods. Details of the RTN l design features are provided in Reference 4. [

l The mid grids for Region 4 have an increased spring force which is designed to reduce rod bow. The Region 4 top grids have a lower spring force to reduce rod bow and have grid sleeves of 304L stainless steel to reduce the potential for stress corrosion cracking.

i l

Table 1 compares pertinent design parameters of the various fuel regions. The Region 4 fuel has been designed according to the fuel performance model in Reference S. As predicted by the Westinghouse.model, (Reference 6) the fuel is designed to operate so that clad flattening will not occur. For all fuel regions, the fuel rod internal pressure design basis, which is discussed and shown acceptable in Reference 7, is satisfied.

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p Westinghouse's experience with Zircaloy clad fuel is described in WCAP-8183,

" Operational Experience with Westinghouse Cores," Reference 8, which is updated annually.

2.2 NUCLEAR DESIGN The Cycle 2 core loading is designed to meet a Fg (z) x P ECCS limit of 5 2.32 x K(z). The core loading pattern contains 256 burnable absorber (BA) rods located in 32 BA rod assemblies. The core loading pattern and the i

location of the BA rods are shown in Figure 1.

Adherence to thegF limit is obtained by using the Fg Surveillance Technical Specification described in Reference 9. Fg surveillance replaces l the previous F surveillance by comparing a measured gF , increased to account for expected plant maneuvers, to the gF limit. This provides a more j convenient form of assuring plant operation below thegF limit while retaining the intent of using a measured parameter to verify operation below Technical Specification limits. F surveillance is only a change to the 0

plant's surveillance requirements and as such has no impact on the results of l the Cycle 2 analysis or safety parameters. l Relaxed Axial Offset Control (RA0C) will be employed in Cycle 2 to enhance j operational flet'bility during non-steady state operation. RAOC makes use of available margin by expanding the allowable al band, particularly at reduced power. The RAOC methodology and application is fully described in Reference

9. The analysis for Cycle 2 indicates that no change to the safety parameters is required for RAOC operation. During operation at or near steady state equilibrium conditions, core peaking factors are significantly reduced due to the limited amount of xenon skewing possible under these operating conditions. The Cycle 2 Technical Specifications recognize this reduction in core peaking factors through the use of a Base Lead Technical Specification.

Table 2 provides a summary of the Cycle 2 kinetics characteristics compared with the current limits based on previously submitted accident analyses, s7m+mm 4

! )

Table 3 provides the control rod worths and requirements at the most limiting l condition during the. cycle (end-of-life). The required' shutdown margin is based on previously submitted accident analysis. . The available-shutdown  !

margin exceeds the minimum required. ,

Rod insertion limits have been deepened for power less than 100% rated thermal power. The associated Technical Specification changes are addressed in Section 4.0 of this report.

2.3 THERMAL AND HYORAULIC DESIGN ,

The thermal hydraulic methodology, DNBR correlation and core DNB limits used-  !

for Cycle 2, are consistent with the licensing submittal (2) . The thermal l hydraulic analyses used for Cycle 2 are based on reduced design flow rates l (373,200 gpm thermal design flow, 387,600 gpm minimum measured flow) in  !

l comparison to Reference 2. No significant variations in thermal margins will l result from the Cycle 2 reload. Sufficient DNB margin exists to satisfy the design criteria (2,12) for the Cycle 2 reload core.

The thermal-hydraulic methods used to analyze axial power distributions generated by the RAOC methodology are similar to those used in the Constant Axial Offset Control (CAOC) methodology. Normal operation power distributions are evaluated relative to the assumed limiting normal operation power distribution used in the accident analysis. Limits on allowable operating axial flux imbalance as a function of power level from these considerations I were found to be less restrictive than those resulting from LOCA F g considerations.

I The Condition II analyses were evaluated relative to the axial power distribution assumptions used to generate DNB core limits and resultant l Overtemperature Delta-T setpoints (including the f(AI) function). The l Ovetemperature Delta-T functions supplied in Section 4.0 and Appendix A include a change to the f(AI) function and ensures.that all criteria will be satisfied during Condition II transients.

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3.0 POWER CAPABILITY AND ACCIDENT EVALUATION l

3.1 POWER CAPABILITY I

i The plant power capability has been evaluated considering the consequences of  !

those incidents examined in the FSAR(2) using the previously accepted design.

basis. It is concluded that the core reload will not adversely affect the ability to safely operate at the design power level (Section.l.0) during Cycle

2. For the overpower transient, the fuel centerline temperature limit of 4700 F can be accommodated with margin in the Cycle 2 core. The time dependent densification model(10) was used for fuel temperature evaluations. The LCCA limit at rated power can be met by maintaining Fg(z) at or below 2.32 x K(z).

l 3.2 ACCIDENT EVALUATION The effects of the reload on the design basis and postulated incidents analyzed in tne FSAR(2) were examined. Also, evaluations were perfcrmed for the standardized pellets, the RTNs, the smaller rod plenum spring, the long tapered end plugs and the reduced rod bow grids as described in Section 2.1.

In all cases, it was found that the effects were accommodated within the conservatism of the initial assumptions used in (1) the previous applicable l safety analysis, (2) the safety evaluation performed in support of the RTD Bypass Elimination licensing submittal (13) , (3) the safety evaluation performed in support of the UHI Elimination licensing submittal I14) , and (4) the safety evaluation performed in support of the Low-T Setpoint M

Modification (15) ,

A core reload can typically affect accident analysis input parameters in the l following areas: core kinetic characteristics, control rod worths, and core peaking factors. Cycle 2 parameters in each of these three areas were examined as discussed in the following subsections to ascertain whether new accident analyses were required.

5700L6-870904 g

Although the Overtemperature Delta-T trip provides protection for several events in the FSAR, the f(41) function is not explicitly modelled.

Therefore, no reanalysis is required'for the TechMeal. Specification change as.

noted in Section 4.0 and Appendix A.

3.2.1 KINETICS PARAMETERS Table 2 is a summary of'the kinetics parameters current limits along with the associated Cycle 2 calculated values. All of the kinetics values-fall within the bounds of the current safety limits.

3.2.2 CONTROL ROD WORTHS Changes in control rod worths may affect differential rod worths, shutdown l

margin, ejected rod worths, and trip reactivity. ' Table 2'shows that the maximum differential rod worth of two RCCA control banks moving together in their highest worth region for Cycle 2 meets the current limit. Table 3 shows that the Cycle-2 shutdown margin requirements have been satisfied. Table 4 is a summary of the current limit control rod ejection analysis parameters and the corresponding Cycle 2 values. The ejected rod worths are within the current limits.

3.2.3 CORE PEAKING FACTORS Peaking factors for the dropped RCCA incidents were evaluated based on the NRC approved dropped rod methodology described in' Reference 11. Results show that DNB design basis is met.

The peaking factors for steamline break.and control rod ejection have been l.

evaluated and are within the bounds of the limits of the licensing submittal.

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a; 4.0 TECHNICAL SPECIFICATION CHANGES To ensure that plant operation is . consistent with.the desigr, and safety evaluation conclusion statements made in this report and to ensure that these conclusions remain' valid, several technical specifications changes will be.

needed for Cycle 2. These changes are presented in Appendix A and include:

1. Axial Flux Differences -RA00, Heat Flux Hot Channel Factors

2. F 5 4 surveillance

. Base Load Tech Specs

4. Rod Insertion Limits

5. OTAT f1(AI) 1 6700L4-570918 6 lJ o__------- '

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5.0 REFERENCES

1. Bordelon, F.M., et. al., " Westinghouse Reload Safety Evaluation Methodology", WCAP-9273-A, July, 1985. ..

2. Catawba Nuclear Station, Units 1 and 2, " Final Safety Analysis Report,"

Docket No. 50-413 and 50-414.

3. Letter from E. P. Rahe, Jr. (Westinghouse) to L. E. Phillips (NRC), April 12,1984,NS-EPR-2893,

Subject:

Fuel Handling Load Criteria (6g vs 4g).

4. Davidson, S. L., Ed., " Reference Core Report VANTAGE 5 Fuel Assembly,"

WCAP-10444-P-A, September 1985.

l

5. Miller, J.V., (Ed.), " Improved Analytical Model used in Westinghouse Fuel Rod Design Computations", WCAP-8785, October, 1976.

6. George, R.A., (et, al.), " Revised Clad Flattening Model, WCAP-8377 (Proprietary) and WCAP-8381 (Nen-Proprietary) July, 1974. i

7. Risher, D. H., (et. al.), " Safety Analysis for the Revised Fuel Rod Internal Pressure Design Basis," WCAP-8964, June, 1977.

8. Skaritka, J., " Operational Experience with Westinghouse Cores" (through December 31, 1986), WCAP-8183 (Non-Proprietary), Revision 15, July, 1987.

9. Miller, R. W., (et al.), " Relaxation of Constant Axial Offset Control-Fg Surveillance Technical Specification," WCAP-10217-A, June, 1983.

l

10. Hellman, J.M. (Ed.), " Fuel Densification Experimental Results and Model for Reactor Operation", WCAP-8219-A, March, 1975.

11. Morita, T., Osborne, M. P., et al., " Dropped Rod Methodology for Negative Flux Rate Trip Plants," WCAP-10298-A (Non Proprietary), June, 1983. l

12. Letter from E. P. Rahe, Jr. (Westinghouse) to H. Berkow (NRC),

NS-NRC-86-3116, March 25, 1986, Westinghouse Response te Additional Requests on WCAP-9226-P/WCAP-9227-NP, " Reactor Core Response to Excessive Secondary Steam Release," (Non-Proprietary).

13. Duke Power Company Transmittal to NRC, "RTD Bypass Elimination for Catawba Units 1 and 2," July 22, 1987.

14. Duke Power Company Transmittal to NRC, " Catawba Nuclear Station Safety Analysis for UHI Elimination," June 1987.

15. Westinghouse Transmittal to Duke Power, " Safety Evaluation for Proposed 4

Feedwater Isolation on Reactor Trip / Low T"V9 Modification," DAP-87-555, April 1987.

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.i TABLE 1 q

CATAWBA UNIT 2 - CYCLE 2 l j

FUEL ASSEMBLY DESIGN PARAMETERS-11 Region- l' 2 3- 4A' 48

• i Enrichment-(w/oU-235)+ 1.61  ; 2.40 - 3.10 3.20 3.40.

Density (% Theoretical)* 95.22 94.92 95,03 95.00 '95.00 t

Number of Assemblies 1 64 '64 48 16

'l 1 Approximate Burnup at++ 12600* 16000 12000 0! O Beginning of Cycle 2 (MWD /MTU) 1 l

Approximate Burnup at++ 21900 25700- 24500 12900- .10600 End of Cycle 2 1 I

(MWD /MTU) 1

• The burnup noted is for the Region 1 fuel assembly being used and is.

not the average for the whole region. i

+ Fuel Regions 1, 2 and 3 values are as-built. .j

++ Based on EOC1 =.14000 MWD /MTV, E002 = 11500 MWD /MTU

$700L:6-470004 g i

TABLE 2-CATAWBA UNIT'2:- CYCLE'2 KINETICS CHARACTERISTICS

~

Cycle =2 Current Limits Design.

Least Negative Moderator +7 < 70% of RTP +7 < 70% of RTP

. Temperature Coefficient +7 ramp to 0.from' +7 ramp to 0 from (pcm/'F)* 70% to 100% of'RTP 70% to 100%'of RTP DopplerTemperatuSe .

-2.9 to -1.00 -2.9 to -1.00 Coefficient (pcm/ F)*

Least Negative Doppler- -9.55 to -6.05  :-9.55 to -6.05 Only Power Coefficient, Zero to Full Power, ,

(pcm/% power)*

Most Negative Doppler -19.4'to -12.6. .-19.4 to -12.6 Only Power Coefficient, Zero to Full Power (pem/%

power)*

• Minimum Delayed Neutron .44 >.44 Fraction 8,ff,(%)

Minimum Delayed Neutron .55 >.55.

Fraction 8 m (%)

[EjectedR8bfat BOLL Maximum Differential Rod 100 <100 Worth of Two Banks Moving Together(pcm/in)*

• pcm = 10 -5 3, s7aave-37o u 11

I 1

TABLE'3 END-OF-CYCLE SHUTDOWN REQUIREMENTS'AND MARGINS H l

CATAWBA UNIT 2 - CYCLE 2

Control Rod Worth (%Ap) Cycle 1 Cyl_e 2 All Rods Inserted 8.25 7.42 All Rods Inserted Less Worst Stuck Rod 7.01- 26.02 (1)Less10% 6.31 5.42  ;

i Control Rod Requirements Reactivity Defects (Doppler, T"V9, 2.89 3.20 Void, Redistribution) ,

Rod Insertion Allowance- 0.50' '0.50 l '

(2) Total Requirements 3.39 3.70 i

Shutdown Margin [(1) - (2)] (%ap) 2.92 1.72 ]

1 Required Shutdown Margin (%Ap) 1.30 1.30! J l

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' TABLE 4 t

CATAWBA UNIT 2.- CYCLE 2. . I CONTROL ROD. EJECTION ACCIDENT PARAMETERS!

HZP-BOCL Current Limit Cycle 2 , l l

Maximum ejected rod 0.75 <0.75 worth, %Ap Maximum F g(ejected)' .11.0 ,<11.0/ q HFP-BOC i

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Maximum ejected rod 0.23L '0.23

< i worth, %Ap ,

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Maximum Fg (ejected) 5.8 . <5.8 HZP-EOC Maximum ejected rod 0.90 <0.90 ,)

worth, %Ap

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Maximum F0(ejected) 19.0 <19.0 HFP-EOC Maximum ejected rod 0.23 <0.23 worth, %Ap Maximum Fg(ejected) 5.9 <5.9 1

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CORE LCADING PATTERN 14

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j REACTIVITY CONTROL SYSTEMS CONTROL BANK INSERTION LIMITS LIMITING CONDITION FOR OPERATION 4 4

3.1.3.6 The control banks shall be limited in physical insertion as shown in Figure 7 3.1-1g,(U., t l' oud 3.1-lb s un . L G l a

.1 APPLICABILITY: MODES la and 2*#.

.4 ACTION:

f With the control banks inserted beyond the above insertion limits, except, for J

surveillance testing pursuant to Specification '4.1.3.1.2:

1 i

a. Restore tne control banks to within the limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />,  :

or

b. Reduce THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to less than or equal to that {

l fraction of RATED THERMAL POWER which is allowed by the bank position ..

using the above figure, or

c. Be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, i l

l 1

l SURVEILLANCE REQUIREMENTS 1

{-

4.1.3.6 The position of each control bank shall be determined to be within f the insertion limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals ']

when the Rod Insertion Limit Monitor is inoperable, then verify the individual I rod positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, l

"See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

1. With K,ff greater than or ? qual to 1. ,

CATAWBA - UNITS 1&2 3/4 1 . Amendment No.14 (Uni t 1) -

Amendment No. 6(Unit 2)

._______..d

. _ _ m.._ _ m

(Fully Withdrawn)

(79 % , 228) 29 % , 228

- l 200 BANK B 180 -

I MMo,161) 160 (0%,162) i

.2  ;

140 - BANK C i

e ,

G -

l '

7 120 i

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8. 100 - -

ie 8

BANK D g _

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(0%. 47) 40 -

l 20- l I

(30 % 01 I I I I I I I I O 100 40 60 80 O 20 (Fully inserted) Relative Power (Percenti FIGURE 3.11g ROD BANK INSERTION LIMITS VERSUS THERMAL POWER FOUR LOOP OPERATIONAL;7 ii 3/4122 Amendment No. 14 (Unit 1)

CATAWBA UNITS 1 and 2 Amendment No. 6 (Unit 2)-  ;

j

}

l ElEf2 '

(FU Y WITH RAWN) 22 . -

-_ f

• i 220 '. . f (20% 2f8)  ;

f (76%, 228) 1 200 .4 B AN K B _

h d('0% k7) ,/ ,/  ;

j180 '. f' ,y#

= / /

e 160 -

j j E 't ,,CBANKC '

_f('100E '162) ', :/

$ 140 / -

m i=

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9 120 f

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• i f i

( 2100 f f f 2 .

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$ 80

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,! f f h b(0% 72) ,/ f'

• 60 j '

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40  ;

f  ;

j BANK D 20 _

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1. ^

0 - -

10 20 30 40 50 60 70 80 9 100 (FULLY RELATIVE POWER (PERCENT OF RATED THERMAL POWERK INSE ED) s FIGURE 3.1-1b s N

R00 BANK INSERTION LIMITS VERSUS THERMAL POWER FOUR LOOP OPERATION (Unit 2)

Cl,TAWBA - UNITS' 1 AND 2 3/4 1-23 Amendment No. 14 (Unit 1)

Amendment No, 6 (Unit 2) ,

3/4.2 POWER DISTRIBUTION LIMITS ,

/

3/4.2.1 AXIAL FLUX DIFFERENCE (AFD) .I l

,a LIMITING CONDITION FOR OPERATION 1

3.2.1)4( The indicated AXIAL FLUX. DIFFERENCE (AFO) shall be maintained within:

a. theallowedoperationalspacedefined'byFigure3.2-1,(forRAOC  ;

operation, or

b. within a 3% target band about the target flux difference during.  :)

baseload operation.

APPLICABILITY: MODE 1, above 50% of RATED THERMAL POWER 0" 't lj.*

ACTION:  !

a. ForRAOCoperationwiththeindicatedAFDoutsideofthefigure3.2-1,(

limits,

1. Either restore the indicated AFD to within the. Figure 3.2-4( '

limits within 15 minutes, or i

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER '

(. within 30 minutes and reduce the Power Range Neutron Flux-High Trip setpoints to less than or equal to 55% of RATED THERMAL-POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b. For Base Load operation above APL ND** with the indicated AXIAL FLUX DIFFERENCE outside of the applicable target banc about the target flux difference:

1. Either restore the indicated AFD to within the target band limits within 15 minutes, or j

2. Reduce THERMAL POWER to less than APL"O of RATE 0' THERMAL POWER and discontinue Base Load operation:within 30 minutes.  ! ,

c. THERMAL POWER shall not be increased above 50% of RATED THERMAL PCWER unlesstheindicatedAFDiswithintheFigure3.2-1,(limits.

• See Special Test Exceptions Specification 3.10.2.

• "APL" is the minimum allowable power level for base load operation 'and 'will l be provided in the Peaking Factor Limit Report per Specification'6.9.1.9. .

l CATAWBA - UNITS 1&2 3/4 2-1 Amendment No.14 (Unit 1)'

Amendment No. 6 (Unit 2)

i l

POWER DISTRIBUTION LIMITS l LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 4.2.1.k1 The indicated AFD shall be determined to be within its limits during )

POWER OPERATION above 50% of RATED THERMAL POWER by:

a. Monitoring the indicated AFD for each OPERABLE excore enannel:  ;

I

1) At least once per 7 days when the AFD Monitor Alarm is OPERABLE. j and l

)

2) At least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after restoring l the AFD Monitor Alarm to OPERABLE status. l 1

b. Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereaf ter, when the AFD Monitor Alarm is inoper-able. The logged values of the indicated AFD shall be assumeo to exist during the interval preceding each logging. i

c. The provisions of Specification 4.0.4 are not applicable. l 4.2.1.t.2 The indicated AFD shall be considered outside of its limits when at least two OPERABLE excore channels are indicating the AFD to be outside the limits. .

j 4.2.1 4 3 When in Base Load operation, the target axial flux difference of j each OPERABLE excore channel shall be determined by measurement at least once  !

per 92 Effective Full Power Days. The provisions of Specification 4.0.4 are i not applicable.

4.2.1.h.4 When in Base Load operation, the target flux difference shall be updated at least once per 31 Effective Full Power Days by either determining j the target flux difference in conjunction with the surveillance requirements of j Specification 3/4.2.2 or by linear interpolation between the most recently mea- j sured values and the calculated value at the end of cycle life. The provisions y of Specification 4.0.4 are not applicable.

l 3

l I

i CATAWBA - UNITS 1&2 3/4 2-2 Amendment No.14(Unit 1) l Amendment No. 6(Unit 2) 1 i

(

t-1 l i  !

l e '

J w

c 3 .l

< 1 0 l C l W $ ,  !

C 2

1. 5 '

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( 20, 100) * (10, 1001 ;1 100 -

1 1 UN ACCEPTABLE '  ! :)

UNACCEPTABLE OPERATION OPERATION ,,

\.

80 -

ACCEPTABLE OPERATION 1

il 60 -

50 - (21, 50) l (-36, 50) i 40 -

l I

l 20 -

l I I I l I I I I 0 10 20 30 40 50 30 20 -10 0 i

' 50 40 Flux Difference (al)%

1 i

FIGURE 3.21)(

AX1AL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL PQW 1

l

- - - - -~m a _o a OM 8-g Amendment.No. a14

-- __ (Unit 1) m.

POWER DISTRIBUTION LIMITS g AXIAL FLUX DIFFERENCE (UNIT 2)

LIMITING CONDITION FOR OPERATION- ,

N

3. 1. 2 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maint ned within the llowing target band (flux difference units) about the tar t flux diffe nce:

a. 5% for Cycle 1 core average accumulated burnup o less than or ual to 5000 MWD /MTU; l b. +34, -9% for Cycle 1 core average accumulate urnup of greater than 000 MWD /MTU; and

c. +3%, -1 for subsequent cycles.

The indicated AFD may eviate outside the.above equired target level at greater than or equal to 50% b less than 90% of RATE THERMAL POWER provided the:inci-cated AFD is within the ceptable Operation imits of Figure 3.2-lb and the l cumulative penalty deviati n time does not ceed'1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during the previous 4 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

tside e above required target band at greater The indicated AFD may deviate than 15% but less than 50% of RA DT RMAL POWER provided the cumulative-penalty deviation time does not e d 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ( '.

APPLICABILITY: MODE 1, above 15 of ATED THERMAL POWER (Unit 2).* l ACTION: s

a. With the indicat AFD outside o the above required target band and with THERMAL PO R greater than or qual to 90% of RATED THERMAL F0WER, within 15 min es, either:

1. Restor the indicated AFD to withi. the target band limits, or

2. Re ce THERMAL POWER to less than 904 f RATED THERMAL POWER,

b. With he indicated AFD outside of the above r uired target band for '

mor than 1 nour of cumulative penalty deviatio times during the pr vious 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or outside the Acceptable Oper ion Limits of gure 3.2-lb and with THERMAL POWER less than 9 ut equal to or j greater than 50% of RATED THERML POWER, reduce:

p

/ 1. THERMAL POWER to less than 50% of RATED THERMAL P ER within

/ 30 minutes, and 1

i

• See Special Test Exceptions Specification 3.10.2.

1 CATAWBA - UNITS 1&2- 3/4 2-4 Amendment No.14 (Unit 1)' l Amendment No. ' 6 (Unit 2)

- - __-Q

lD l

POWER DISTRIBUTION LIMITS h thL l

. i. 1

~

LIMITING CONDITION FOR OPERATION 1 1

1. CTION (Continued)  !

2. The Power Range Neutron Flux * - High Setpoints: to 1 ss than or :

equal to 55% of RATED THERMAL POWER within the ne 4. hours.

c. With the indicated AFD outside of the above require target band for +3 more'than 1-hour of cumulative penalty dev'iation me during the pre- I ous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and with THERMAL POWER less than  % but greater;than-1 of RATED' THERMAL' POWER, the THERMAL POWER all not be increased

~

equ to or greater than.50% of RATED THERMAL' OWER until the indi- 1 cated FD is within the above required targ band.

SURVEILLANCE RE0VIR ENTS 1

4.2.1.1.2 The' indicated FD shall be determi d to be within its limits curing l l I

POWER OPERATION above 15% f RATED THERMAL P WER by:

a. Monitoring the indi ted AFD f each OPERABLE excore channel:

N . . . +

1

1) At least once per sda when the AFD. Monitor Alarm is OPERABLE,  ! ,

and  ; l j

\

At least once per our or the first' 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ' af ter rest'oring

~

2) the AFD Monitor arm to PERABLE status.  !

N

b. Monitoring and log ng the indic ed AFD for each OPERABLE excore:

channel at least nce per hour for he' first 24. hours and:at least once per 30 min es thereafter, when 'the AFD . Monitor Alarm ~ is inoper- ~ '

able. The lo ed values of.'the indic ed.AFD shall be'assumea.to.

exist during he interval preceding eaci logging. l 4.2.1.2.2 The indi ted AFD shall be considered out 'de ,of its target' band when two or more. ERABLE!excore channels are indicati the'AFD'to ce outside i the target band. Fenalty deviation outside of the above required target cano -) ,

shall be accum ated on a time basis of:

a. O minute penalty deviation for each 1 minute of ER OPERATION-

,' utside of the target band at . THERMAL POWER levels e al.to or above

/ 50% of RATED THERMAL' POWER,.and

/

• S veillance testing of the Power Range Neutron' Flux Channel may.be p formed rsuant to Specification 4.3.1.1 provided the indicated AFD is maintal ed within the Acceptable Operation Limits of Figure 3.2-lb. A total of 16 urs operation may be accumulated with the AFD outside of the'above required.ta. et band during testing without penalty deviation.

1 CATAWBA'- UNITS 1&2 ~3/4 2-4a- Amendment No.14 (Unit 1)-  !

Amendment No. . 6'(Unit .2)

POWER DISTRIBUTION LIMITS i VEILLANCE REQUIREMENTS (Continued) ,

.z

b. e-half minste penalty deviation for each 1 minute of POWER OPERATI0tl }

. side of tne target band at THER POWER levels between 157. and 50b RATED THERMAL POWER.

\

4.2.1.2.3 ThetargeN1uxdifference each OPERABLE excore enannel shall be determined by measuremeM, at least o e per 92 Effective Full' Power Days. The provisions of Specificati,o 4.0.4 re not applicable.

4.2.1.2.4 The target flux di' ey nce shall be updated at least once per i 31 Effective-Full Power Day by ei e determining the target flux difference pursuant to Specification .2.1.2.3'a e or by linear interpolation between i" the most recently measu d value and 0% a the end of cycle life. The provi-'

sions of Specificatic 4.0.4 are not applici e.

)

1 YE.k't b

'I l

CATAWBA - UNITS 1 & 2- 3/4 2-4b Amendment No.14 (Unit 17 Amendment No. 6-(Unit 2)^

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0 50 40 30 20 10 0 10 '20- =30' 40- 50 FLUX DIFFERENCE (61) % J FIGURE 3.2-1b AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (Unit 2)

Amendment .No. 14 (Unit'_b- ';

3/4'2-4c CATAWBA'- UNITS 1 AND 2 . ,

~ Amendment Nd.: 16 4 (Unit 2).

POWER DISTRIBUTION LIMITS 3/4.2.2 HEATFLUXHOTCHANNELFACTOR-Fn(Z)[ w -

/f .

f LIMITING CONDITION FOR OPERATION 3.2.2 4 F g(Z) shall be limited by the following relationships: ]

i Fg (Z) 1 [2.32] [K(Z)] for P > 0.5 P

Fq (Z) 5 [4.64] [K(Z)] for P 1 0.5 l

, and Where: P = THERMAL POWER-RATED THERMAL POWER l K(Z) = the function obtained from Figure 3.2-2.for a given core height location.

APPLICABILITY: MODE 1 ACTION:

With Fq (Z) exceeding its limit:

a. Reduce THERMAL POWER at least 1% for each 1% q F (Z) exceeds the limit j j within 15 minutes and similarly redt ce. the Power Range. Neutron .

Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER OPERATION l may proceed for up to a total of 72-hours; subsequent POWER OPERATION may proceed provided the Overpower aT Trip Setpoints (value of K ) have i been reduced at least 1% (in aT span) for each 1% Fq(Z) exceeds the 1 limit, and

b. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced. limit required by ACTION a., above; THERMAL POWER may then be increased provided Fq (Z) is demonstrated through incore mapping to be within its limit.

1 l

CATAWBA - UNITS 1 & 2 3/4 2-5 Amendment No.14

' Amendment No. (Unit6(Unit

2) 1) . ;

l I

~

POWER DISTRIBUTION LIMITS 0

i SURVEILLANCE REQUIREMENTS c

q 4.2.2.A.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.1.2 For RAOC operation, g(F (z) shall be evaluated to determine if Fg (z) is within its limit by:

a. Using the movable incore detectors to obtain a power distribution map at any THERMAL' POWER greater than 5% of RATED THERMAL-POWER. .j y

b. Increasing the measured gF (z) component of the power distribution )

I map by 3% to account for manufacturing tolerances and'further in-  !

creasing the value by 5% to account for measurement uncertainties.

~

Verify the requirements of Specification 3.2.2.% are ' satisfied.

c. Satisfying the fullowing relationship: ]

2.32 x M z) for P > 0.5 ,

Fq "(z) 1 P x W(z) ll M 2.32 x K(z)

Fq (z) 1 for P 1 0.5 l W(z) x 0.5 ,

where F"(z) is the measured F q (z) increased by the allowances for manufacturing tolerances and measurement uncertainty, 2.32 is the 'l Fg limit, K(z) is given in Figure 3.2-2, P is the relative THERMAL POWER, and W(z) is the cycle dependent function that accou'nts for power distribution transients encountered during normal operation.

This function is given in the Peaking Factor Limit Report as per Specification 6.9.1.9.

d. Measuring F "(z) according to the following schedule:

9

1. Upon achieving equilibrium conditions after exceeding by 10% or ,

more of RATED THERMAL POWER, the THERMAL POWER at which F g (z) was last determined,* or

) 2. At least once per 31 Effective Full Power Days, whichever occurs I first.

f

\

• During power escalation at the beginning of each cycle, power level may be increased until a power level for extended operation has been achieved and a #

power distribution map obtained.  ;

CATAWBA - UNITS 1&2 3/4 2-6 Amendment No.14 (Unit 1)-

Amendment No. 6 (Unit 2), .;

j l

-] ,

i POWER DISTRIBUTION LIMITS j i"

j SURVEILLANCE REQUIREMENTS (Continued) j

e. With measurements indicating maximum [-F"(z) over z N(z) )

has increased since the previous determination of F (z) either of

-the following actions shall be taken: 3 I

1) F M

q (z) shall-be increased by 2% over that specified in .] -

Specification 4.2.2.A.2c., or. f

2) F N

q (z) shall be measured at least once per 7 Effective Full j Power Days until two successive maps indicate that ]

is not increasing. I maximum F (z) over z K(z) q

f. With the relationships.specified in Specification 4.2.2.$,.2.c. above l

, l not being satisfied:

f.

Calculate the percent F (z) exceeds its limit by the following (

1) q 1 expression: J r g- T d

[ maximum F (z) x W(z I - 1p 100 for P'> 0.5 322 x g(7)

/  !

(ove'r-I

" l M

[ maximum F g (z) x W(z5 , 1 x 100 for P < 0.5 over z' 2.32 x g(z) /

0.5 - ,

1-

2) One of the following actions shall be taken:

a) Within 15 minutes, control the AFD to within new AFD-limits which are determined by reducing the AFD' limits of 3.2-la by' 1% AFD for each percentq F (z) exceeds its limits as deter-mined in Specification 4.2.2.12f.1). Within 8' hours, reset -i the AFD alarm setpoints to these. modified limits, or b) Comply with the requirements of Specification'3.2.2.A for Fq (z) exceeding its limit by the percent calculated aoove, or c)_ Verify that the requirements'of Specification 4.2.2.K.3'fo'r .,

Base ' Load operation are satisfied and enter Base Load operatior -

l, CATAWBA - UNITS 1 & 2 3/4 2-7 Amendment No.14 (Unit 1)

Amendment No. 6 (Unit 2)  !

___ ___ J

J 1

POWER DISTRIBUTION LIMITS 1

.t l1 e

SURVEILLANCE REQUIREMENTS (Continued)=

1,

g. The 1imits specified in Specifications 4.2.2.12c. , 4.2.2j 2e , and 4.2.2.12f. . above are not'. applicable in the' following core plane  ; j regions: +)

1. Lower core region from 0 to 15%, inclusive .  !;l

2. Upper core region from 85 to 100%,. inclusive. 1 4.2.2.1 3 Base Load operation-is permited at powers above APL if the following.

conditions are satisfied: .l 4

a. Prior to entering Base Load operation, maintain THERMAL POWER'above-APL ND and less than or equal to that allowed by Specification 4.2.2.X 2- )

for at least the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Maintain Base Load operation-surveillance (AFD within 3% of target flux difference) during this l 1

time period.' Base load operation is then permitted providing THERMAL i .1 NO BL ND POWER is maintained between APL and APL or between APL and I

100% (whichever is most limiting) and FQ surveillance is maintained OL pursuant to Specification 4.2.2.% 4. APL is defined as: (<

APL BL = minimum g

-(2.32 x C ). -

3 x 100%  !~

i ver Z M pq(Z) x W(Z)BL i where: FM (z) is the measured Fq (z)' increased by the allowances for manufacturing tolerances and measurement uncertainty. The Fg limit is 2.32. K(z) is given in Figure 3.2-2. W(z)BL1 is the cycle-dependent, i' function that accounts for limited power distribution transients -

encountered during base load operation. . The function-is'given in the Peak Factor Limit Report as 'per Specification 6.9;1.9.

b. Qurirg Base Load operation, if the THERMAL POWER is decreased below .

APL"0 thentheconditionsof4.2.2.%3.ashall.besatisfiedbefore Ii re-entering Base Load operation. i 1

4.2.2.K.4 During Base Load Operationg F (Z) shall be evaluated to determine if F (Z) is within its limit by:

q

a. Using the movable incore detectors to obtain a power. distribution e ND map at any THERMAL POWER above APL ,

b. Increasing the measured Fg (Z) component of the power distribution map by 3% to account for manufacturing tolerances.and further increasing the value by 5% to account for measurement uncertainties. Verifyfthe requirements of Specification 3.2.2 5 are satisfied.

l CATAWBA - UNITS 1 & 2 3/4 2-7a Amendment No.14 (Unit 1)'

, Amendment No. 6 (Unit 2)-

1

9 I

POWER DISTRIBUT M ,IMITS i

SURVEILLANCE REQUIREMENTS (Continued)

c. Satisfying the following relationship:

M Fq (7) ~< . ( 2. 32 x @for P: > APL"O i P x W(Z)BL' where:

M F (Z)-is the measured Fq (Z). The F q limit is~2.32.

K(Z).is given in Figure 3.2-2. P is the relative THERMAL POWER.'  !

W(Z)gt is the cycle dependent function'that accounts for limited power [ .j distribution transients encountered during normal operation. This function is'given in the Peaking Factor. Limit Report' as per lOl Speci fication 6. 9.1. 9. -i M

d. Measuring.F n (Z) in' conjunction with target flux difference deter-mination according to the following schedule: j

1. Prior to entering BASE LOAD operation after satisfying: surveil--

lance 4.2.2.W.3 unless a full-core: flux map'has been taken.-in'the previous 31 EFPD with'the' relative thermal.p'ower having been ND maintained above APL for the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to mapping, and. , H A i

2. At least once per 31 effective ful.1 power days'. -

e. With measurements indicating i

maximum F (z) over I -E K(z)

'I~

has increased since the previous determination.F'M(Z) either of t'ne

~

following actions shall be taken: k

1. F"(Z) shall be increased by 2 percent over that specified'in 4.2.2.N.4.c,or  ; ._ l

2. F (Z) shall be measured at least once per 7 EFPD until 2 successive maps indicate that i maximum F (z) over Z ( K(z) ) is not increasing.

^

f. With the relationship specified.in 4.2.2 X.4c.above not being satisfied, either of the following actions sh'all be ~ taken:

1. Place the core in an equilibrium condition where the limit in 4.2.2.X.2c is satisfied, and remeasure F (Z), 'or p

CATAWBA - UNITS 1 & 2- 3/4 2-7b' 4 Amendment No.14 (Unit:1)'-  :,

Amendment'No. 6 (Unit 2).

i. -

POWER DISTRIBUTION LIMITS 3

SURVEILLANCE'E' REQUIREMENTS (Continued)

2. Comply with the requirements of Specification'3.2.2.5 for.

F (Z) exceeding its limit by the percent calculated witn 9

the following expression:

F (Z) x W(Z)BL ] ) -1 ] x 100 for,P~> APL NO '

[(max. over I of [ 2.32 x-K(Z)- .

.p

g. The limits speci fied in 4.2. 2.)(.4c. , 4.2. 2.g.'4e. , and 4. 2. 2.X. 4f.

above'are not applicable in the following' core plan' regions:

'1. Lower core' region 0 to 15' percent, inclusive.

2. Upper core region 85 to 100 percent, inclusive.

4.2.2.K 5 When F (Z) is measured for reasons other than'me'eting the requirements 1 9

of Specification 4.2.2.](.2 an overall measured F q(z)~shall . be obtained from a-power -

~

distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

i s.

-i

-t l

l CATAWBA - UNITS.1 & 2' 3/4 2-7c Amendment No.14 (Unit 1).

' Amendment No. 6 (UnitL 2);

q f f POWER DISTRIBUTION LIMITS-HEAT FLUX HOT CHANNEL FACTOR - F (Z) (Unit 2)

LIMITING CONDITION FOR OPERATION 1 2.2.2 F (Z) shall be limited by the following relationships:

9 F0 (Z) 1 (2.32) [K(Z)] for P > 0.5 P

'x N's F9 (Z) 1 [4.64] [K(Z)] for.P 1 0.5 N , and 1 NWhere: P _ RATED THERMAL POWER THERMAL POWER K = the function obtained from .igure 3.2-2 for a given core hei. t, location.

i N APPLICABILITY: MODE 1 Unit 2).

ACTION:

)

With F (Z) exceeding its limit:  !

9 ri east 1% for each 1%'Fq (Z) exceeds the. limit l

a. Reduce THERMAL POWER a within 15 minutes and im arly reduce the Power Range Neutron .

Flux-High Trip Setpo nts w1 in the next'4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER OPERATION may proceed for up o'a tota of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent POWER OPERATION may proceed provi ed the Overp er .1T Trip Setpoints (value.of K4 ) have been reduced at east 1% (in .1T an) for each 1% F9 (Z) exceeds the limit, and ,

i

b. Identify a correct the cause of the ut-of-limit condition prior i to incre ing THERMAL POWER above the r uced limit required by ACTION ., aoove; THERMAL POWER may then e-increased provided F (Z) s demonstrated through incore mappi to be within its limit.

9

/ .

/

(

L I CATAWBA - UNITS 1 & 2 3/4 2-7d Amendment No.14 (Unit'1)-

Amendment No. 6 (Unit 2)

] ..

POWER DISTRIBUTION LIMITS

. SURVEILLANCE' REQUIREMENTS ]

4.2.2.2.l' The provisions of Specification 4.0.4 are not' applicable. .]

4.2.2.2.2 F shall.be evaluated to determine'if.F 9 (Z) is within its limit.by:

c

]

Using.the movable incore detectors to-obtain a power di ribution ss a. i

\ map at any THERMAL POWER greater than 5% of RATED THER L POWER,

. Increasing the measured.F xy component of.the power - distribution map by 3% to account for manufacturing tolerances an further increasing'. -[

l the valuelby 5% to account for measurement unce ainties,. ,

L

c. Co aring the F xy computed (F )..obtained i peci fication 4. 2,2. 2. 2b..,

abo to:

,/ y 1). Th F,[limitsforRATEDTHERMAL-P ER (F P) for.thel appropriate I

meas 'ed core planes given in Sp cification 4.2.2.2.2e. and f.,

below, nd'

2) The relat nship:

~l 1

F' xy

= ' RTP.. [1+0.'2( )],

l for fractional THERMAL POWER operation Where.F*Y is the' jmi expressed as a. fun on of'FRTP'and xy PLis the. fraction of RATED THERMAL POWER at hic ( was measured.

d. Remeasuring F acc ding.to e following schedule:

1) When F greater than the limit for the appropriate measure core plane but-less tha the F relationship,: additional j C

powergistributionmapsshallbetaen nd F Y compared to F

• Y and either:

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding by  % of. RATED NERMAL POWER or greater, the THERMAL. POWER a which F C was last determined, or

]

b) At least once per 31 EFPD, whichever occur irst.

?

l

~1 l

CATAWBA ~- UNITS 1 & 2 3/4 2-7e ' Amendment No, ~14 (Unit '1)

Amendment No. 6 (Unit 2).. l

O o

+

, pdek POWER DISTRIBUTION LIMITS I i SURVEILLANCE REQUIREMENT $'(Continued)

~

l P

2) When the xF . is less than or equal to the F limit for t.

appropriate measured core plane, additional power distri tion RTP L

' maps shall be taken and F compared to F and F xy least once per 31 fiFPD.

RTP The F provided for

. xy limits for R3TED THERMAL POWER (Fxy ) shall all core planes containing Bank "D" control rods a all unrodded

('  !

l cc e planes in,a Radial Peaking Factor Limit Rep rt per Specifica-tion .9.1.9; ,,

f. The F 'mits of Specification 4.2.2.2.2e. above, are not applicable xy in the foil ng core planes regions as tr asured in percent of core j height from ttom of the fuel:

1) Lower core re ion from 0 to 15% inclusive, f x l 2) Upper core region 4 rom 85 to 00%, inclusive, f .

\

Grid plane regions at 7 ! 2%, 32.1 2%, 46.4 2%, 60.6

3) 2%

and 74.9 t 2%, inclusiv ,tand Core plane regions k

4) about the bank dem dthin t 2% core height (t 2.88 inches) position;of df the Bank "D" control rods.

c  %

g. With F ~ exceeding F , the' effects of F on F to determine if Z) is within its limits. \ q(Z) shal.1 be evaluated 4.2.2.2.3 When qF (Z) is easured for other than F determinations, an overall l 1 measured F (Z) shall b obtained from a power distribution maiNand increased Q  %

by 3% to account for manufacturing tolerances and further increaigd by 5% to ecount for measur ment uncertainty.

/

1 1

CATAWBA - UNITS 1 & 2- 3/4 2-7f Amendment No.14 (Unit 1)

Amendment No. 6 (Unit 2)

1.50 --

F.:sr_-

1.25 1

~  :~

l 1.00 1

01 0.75 ..

(

~

0.50 -CORE HEIGHT K(Z) 0.0 1.00 6.0 1.00 0.25 10.8 0.94 12.0 0.65 0

0 2.0 4.0 6.0 8.0 10.0 12.0

- CORE HEIGHT (FT)

FIGURE 3.2-2 K(Z) - NORMALIZED F g(Z) AS A FUNCTION OF CORE HEIGHT CATAWBA - UNITS 1 AND 2 3/42-8

. g <

d

. .i

}

1 BASES FOR j

.. a L SECTIONS'3,O AND 4.0 1 .-

LIMITING CONDITIONS FOR'0PERATION 1

. i AND- 4 l

1 i ..

I SURVEILLANCE REQUIREMENTS e

s,

.* ;I I.

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L Il 1

3 3/4.2 POWER DISTRIBUTION LIMITS BASES 1

l The- specifications of this section provide assurance of fuel integrity duri'ng Condition I (Normal Operation) and II (Incidents of Moderate Frequency) _,i events by: (1) maintaining the calculated DNBR in the core greater than or ecual to design limit DNBR during normal _ operation and in short-term transients, and (2)_ limiting the fission gas release, fuel pellet temperature, and cladding 1 mechanical properties to within assumed design. criteria. In addition, limiting the peak linear power density' during Condition I events provides assurance that the initial conditions assumed for the LOCA analyses are met and the ECCS ,

acceptance criteria limit of 2200*F is not exceeded.

Th'e definitions of certain hot channel and peaking factors as used in l these specifications are as follows:  ;

Fg (Z) Heat Flux Hot' Channel Factor, is defined as the maximum local heat flux on the surface of a fuel rod at ccre elevation Z divided by .the i average fuel rod heat flux, allowing for manufacturing tolerances on  :

fuel pellets and rods; F Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of H

the integral of linear power along the rod with the highest integrated i power to the average rod power; and

(

FjY(!) -- te tdi:1 Pcning Factcc;-4s-defined-as-the--ratio-of" peak-power density nerage peeer density 4a the heri:Ontal plan Ot-core-el eva t i oH - 1 (Unit 2 Orly). l 3/4.2.1 AXIAL FLUX OIFFERENCE The limits on AXIAL FLUX DIFFERENCE (AFD) assure that the F q (Z) upper bound enveloce of 2.32 times the normalized axial peaking factor is not exceedea during either normal operation or in the event of xenon redistribution following power changes.

Target flux difference is determined at equilibrium xenon conditions.

The full-length rods may be positioned within the cort in accordance with their respective insertion limits'and should be inserted near their normal position for steady-state operation at high power levels. The value of the l target flux difference obtained under these conditions divided'by the f raction i of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER for the associated core burnup conditions. Target flux differences for other THERMAL POWER levels are obtained by multiplying the RATED THERMAL POWER value by the appropriate fractional THERMAL POWER level. The periodic updating of the target flux difference value is necessary to reflect. core burnup considerations.

CATAWBA - UNITS 1 & 2 8 3/4 2-1 Amendment No.14 (Unit l') '

Amendment No. 6 (Unit - 2)

[

POWER DISTRIBUTION LIMITS

(

BASES  ;

AXIAL FLUX DIFFERENCE (Continued) ythoughitisintendedthatUnit2willbeoperatedwiththeAFDwithin l the tartJet band requirea by Specification 3.2.1.2 about the target flux aif fer-ence, durh g rapid plant THERMAL POWER reductions, control rod motion will se the AFD to de iate outside of the target band at reduced THERMAL POWER 1 els.

This deviation ill not affect the xenon redistribution sufficiently change the envelope of p\aking factors which may be reached on a subsequ return to RATED THERMAL POWER N (with the AFD within the target band) provi1 fed-the time duration of the deviat' ton is limited. Accordingly, a 1-hour penalty. deviation limit cumulative during previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is provi for operation outside of the target band but with the limits of Figure -lb while at THERMAL POWER l levels between 50% and 90% of' RATED THERMAL POWE For THERMAL POWER levels between 15% and 50% of RATED THEM AL POWER, iations of the AFD outside of the target band are less significan Th enalty of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> actual time reflects this reduced significance.

For Unit 2, provisions for itorin the AFD on an automatic basis are j derived from the plant proces computer thro h the AFD Monitor Alarm. The computer determines the 1- nute average of eae of the OPERABLE excore detector outputs and provides a. alarm message immediately 'f the AFD for at least two of four or two of ee OPERABLE excore channels ar utside the target band and the THERMAL WER is greater than 90% of RATED TH L POWER. During opera-tion at THE POWER levels between 50% and 90% and bet n 15% and 50% RATED (

THERMAL WER, the computer outputs an alarm message when penalty deviation accu ates beyond the limits of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, respecti - y.

Figure B 3/4 2-1 shows a typical monthly target band for Uniw 9 W t power levels below APL , the limits on AFD are defined by Figure 3.2-1W, i.e., that defined by the RAOC operating procecure and limits.

These limits were calculated in a manner such that expected' operational tran-sients, e.g., load follow operations, would not result in tne AFD aeviating I outside of those limits. However, in the event such a deviation occurs, tne snort period of time allowed outside of the limits at reduced power levels will r l

not result in significant xenon redistribution such that the envelope of peaking j i f actors would change sufficiently to prevent operation in the vicinity of tne i I

ND APL power level. {

ND

hpowerlevelsgreaterthanAPL , two modes of operation are  !

permissible; 1) RAOC, the AFD limit of which are defined by Figure 3.2-1X, .and }

2) Base Load operation, which is defined as the maintenance of the AFD within i a :3% band about a target value. The RAOC operating procedure above APL is ND the same as that defined for operation below APL . However. it is possible when following extended load following maneuvers that the AFD limits may result in restrictions in the maximum allowed power or AFD in order to guarantee opera- ,

tion with F (I) less than its limiting value. To allow operation at the maximum j permissible value, the Base load operating procedure restricts the indicated CATAWBA - UNITS 1 & 2 8 3/4 2-2 Amendment No.14 (Unit 1)

Amendment No. 6 (Unit 2)

)

POWER DISTRIBUTION LIMITS 'f

(

BASES AXIAL FLUX OIFFERENCE (Continued)

AFD to relatively small target band and power swings ( AFD target band of :3L APL < power < APL OL or 100% Rated Thermal Power whichever is lower). For Base Load operation, it is expected that w 11 operate within.the target band. Operation outside of the target band for the short time period allowed ,

will not result in.significant xenon redistribution such that the envelope of peaking factors would change sufficiently to- prohibit continued operation in the power region defined above. To assure there is no residual xenon redistri-  !

bution impact from past operation on the Base Load operation, a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> waiting l I

period at a power level above APLNO and allowed by RAOC.is necessary. During. ,

this time period load changes and rod motion are restricted to that allowed by -l the Base Load procedure. After the waiting period extended Base Load operation , i is permissible, j k'-  ; h e computer determines the one minute average of each of the I OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for at least 2 of 4 or 2 of 3 OPERABLE excore channels are: 1) outsice the allowed AI power operating space (for RACC operation), or 2) outside the allowed al target band (for Base Load operation). These alarms are active when power is greater than: 1) 50% of RATED THERMAL POWER (for RAOC operation),

(

or 2) APLNO (for Base Load operation). Penalty deviation minutes for Base Load operation are not accumulated based on the short period of time during which operation outside of the target band is allowed.

3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR. and REACTOR COOLANT SYSTEM i i FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR .

The limits on heat flux hot channel factor, coolant flow rate, and nuclear enthalpy rise hot channel f actor ensure that: (1) the design limits.on ceak ,

local power density and minimum DNBR are not exceeded and (2) in the event of a LOCA the peak fuel clad temperature will not exceec the 2200 F ECCS acceotance criteria limit. ,

Each of these is measurable but will normally only be determined  :

periodically as specified in Specifications 4.2.2 and 4,2,3. This periooic l:

surveillance is sufficient to insure that the limits are maintained provicea:

~

a. Control rods in a single group move together with no individual rod insertion differing by more than : 12 steps, indicated, from the group demand position;

b. Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.6; CATAWBA - UNITS 1 & 2 B 3/4 2-2a Amendment No.14 (Unit:1) '

Amendment No. 6 (Unit 2)

L1

". I :

b,? j?. .. .L.;

. Y 1.00 .

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4 0.70 1

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..j ....j. . Tarp . t 4x oitterence .-

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- 20',. - 10. 0 - 10. +20'. ' -30. ^l

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INDICATED AXlAL FLUX DIFFERENCE v.,..ya . ... e. .n. . .

M : C a'. NO CATED Ax:AL FL.4 :: FFERE*,;I g[: .! -[:.v;., : ;,, . : (Unit 2)

CA1AWBA - UNITS.1 AND 2 8 3/4 2 Amendment No. 14 (Unit 1)

Amendment No. 6 (L' nit 2)

POWER DISTRIBUTION LIMITS l

BASES HEAT FLUX HOT CHANNEL FACTOR, and REACTOR COOLANT SYSTEM FLOW RATE AND NUCLEAR l

ENTHALPY RISE HOT CHANNEL FACTOR (Continueo)

I

c. The control rod insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are maintained; and

d. The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.

F will be maintained within its limits provided Conditions a. through d. j H

above are maintained. As noted on Figure 3.2-3, Reactor Coolant System flow rate and F H may be % raded o m aga nst one ano n er (i.e., a N

l Coolant System flow rate is acceptable if the measured F 4 is also low) to ensure 1 that the calculated DNBR will not be below the design DNBN value. The relaxation ]

of.F H as a function of THERMAL POWER ~ allows changes in.the radial power shape' )

for al.1 permissible rod insertion limits. ]

i R as calculated in Specification 3.2.3 and used in Figure 3.2-3, accounts i for F H less than or equal to 1.49. This value is used in the various accident ]

analyses where F g influences parameters other than DNBR, e.g., peak clad temp-erature, and thus is the maximum "as measuged" value allowed. The rod bow pen-alty as a function of burnup applied for F .1H is calculated with the methods de-scribed in WCAP-8691, Revision 1, " Fuel Rod Bow Evaluation," July 1979 ana tne maximum rod bow penalty is 2.7*. DNBR. Since the safety analysis is performed with plant-specific safety ONBR limits.of 1.49 and 1.47 compared to the design DNBR limits of 1.34 and 1.32, respectively, for the typical and thimble cells. .

nere is a 10*. tnermal margin available to offset the rod bow penalty of 2.7'& ONER.  !

l When an gF measurement is taken, an allowance for both experimental error and manuf acturing tolerance must, be made. An allowance of 5*. is appropriate for l a full-core map taken with the Incore Detector Flux Mapping System, and a 3*. I allowance is appropriate for manufacturing tolerance.  !

Jee-*>and>-1 e hot channel factor F"(z) is measured periodically 'and in-creased by a cycle and height dependent power factor appropriate to either RAOC or Base Load operation, W(z) or W(z)g(, to provide assurance that the limit on j the hot channel factor, F (z), is met. W(z) accounts for the effects of normal 9

operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core. W(z)BL. accounts for-the more restrictive operating limits allowed by Base Load operation which result

) in less severe transient values. The W(z) function for normal operation is l provided in the Peaking Factor Limit Report per Specification 6.9.1.9.

1 i

CATAWBA - UNITS 1.& 2 8 3/4 2-4 Amendment No.14 (Unit 1)

Amendment No. 6 (Unit 2)

L-_-_---_____-

T.

POWER DISTRIBUTION LIMITS 4

BASES FACTOR. and REACTOR COOLANT SYSTEM FLOVA ff ND NUC; EAR HEAT FLUX HOT CH

• r ENTHALPY RISE HOT CHANN?bsF ACTOR (Continued)

For Unit 2 the Radial Peaki - Factor, F '.

t , is measured periodically to provide assurance that the Hot'Channe ctor, F (Z), remains within its limit.

g ,

The F x limit for RATED THERMA ER (F xy s provided in the Radial Peaking-Factor Limit Report-per cification 6.9.1.9 was + ermined from expected power control mane s over the full range of burnup ditions in-the core.

I

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l l

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.1 l

1 CATAWBA - UNITS' 1 & 2 8 3/4 2-4a Amendment'No.14 (Unit 1)

Amendment No. 6 (Unit'2)

- - -- ---.mm__m.______.____ ,_

7 1

l I

POWER DISTRIBUTION LIMITS BASES HEAT FLUX HOT CHANNEL FACTOR, and REACTOR COOLANT SYSTEM FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL F ACTOR (Continued)- '

WhenReactorCoolantSystemflowrate,andFhare. measured,noadditional allowances are necessary prior to comparison with the' limits of Figure 3.2-3.

Measurement errors of 2.1% for Reactor Coolant System total flow rate and 4%

,]

for Fh have'been allowed for in determination of the design DN8R value.

The measurement error for Reactor Coolant System total flow rate'is based '

upon perfornirq a precision heat balance and using the result to calibrate the Reactor Coolant System flow rate indicators. Potential fouling of the feedwater, venturi which might not be detected.could bias the result from the precision heat balance in a nonconservative manner. Therefore,'a penalty of 0.1%-forAny undetected fouling of the feedwater venturi is included in Figure 3.2-3.

fouling which might bias the Reactor Coolant System flow rate measurement-greater than 0.1% can be detected by monitoring and trending various plant performance parameters. If detected, action shall .be taken before performing subsequent precision heat balance measurements, i.e., either the effect of the.

(. fouling shall be quantified and compensated for in the Reactor Coolant System -

flow rate measurement or the venturf shall be cleaned to eliminate the fouling.

The 12-hour periodic surveillance of indicated Reactor Coolant System.

flow is sufficient to detect'only flow degradation which could lead to opera-tion outside the acceptable region of operation shown on Figure 3.2-3.

3/4.2.4 QUADRANT POWER TILT RATIO The QUADRANT POWER TILT RATIO limit assures that the radial, power distribu- i tion satisfies the design values used in the power capability analysis.

Radial power distribution measurements are made during STARTUP testing and periodically during power operation.

The limit of 1.02, at which corrective action is required, provides.ONB i and linear heat generation rate protection _ wi_th x y plane power tilts. A limit of 1.02 was selected to provide an allowance for the uncertainty associated with the indicated power tilt. l The 2-hour. time allowance for operation with.a tilt condition greater'

- than 1.02 but less than'1.09 is provided to allow identification and correction-of a dropped or misaligned control rod. In the event such action does not correct the tilt, the margin for uncertainty on Fq is reinstated by reducing = l the maximum allowed power by 3% for each percent of tilt in excess of 1. ,

For purposes of monitoring QUADRANT POWER TILT RATIO when one excore- .

detector is inoperable, the moveable incere detectors are used to confirm that

/

the normalized symmetric power distribution is consistent with the QUADRANT-t POWER TILT RATIO. . .The incore detector monitoring is done wi,th a full incore

POWER DISTRIBUTION LIMITS BASES QUADRANT POWER TILT RATIO (Continued) flux msp or two sets of four symmetric thimbles. The two sets of four symmetric thimbles is a unique set of eight detector locations. The normal locations are ,

C-8, E-5, E-11, H-3, H-13, L-5, L-11, N-8. Alternate locations are available  ;

if any of the normal locations are unavailable.

3/4.2.5 DNB PARAMETERS l

The limits on the DNB-related parameters assure that each of the parameters are maintained within the normal steady-state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a design limit DNBR throughout each analyzed transient. The indicated T,yg value and the indicated pressurizer pressure value correspond to analytical limits of 594.8*F and 2205.3 psig respectively, with allowance for measurement uncertainty.

The 12-hour periodic surveillance of these parameters through instrur'.at l readout is sufficient to ensure that the parameters are restored within tns'.r limits following load changes and other expected transient operation. Indica- ( j tion instrumentation measurement uncertainties are accounted for in the limits provided in Table 3.2-1.

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l CATAWBA - UNITS 1 & 2 B 3/4 2-6 Amendment No. 24 (Unit 1)

Amendment No.14 (Unit 2)

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SECTION 6.0 l; ADMINISTRATIVE CONTROLS l 4

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ADMINISTRATIVE CONTROLS e

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) l The Semiannual Radioactive Effluent Release Reports shall include a list and I description of unplanned releases from the site to UNRESTRICTED AREAS of radio- )

active materials in gaseous and liquid effluents made during the reporting j period. l The Semiannual Radioactive Effluent Release Reports shall include any changes  ;

made durinc the reporting period to the PCP and to the ODCM, pursuant to Specifi- l cations 6.13 and 6.14, respectively, as well as any major changes to Liquid, l Gaseous or Solid Radwaste Treatment Systems, pursuant to Specification 6.15.  !

It shall also include a listing of new locations for dose calculations and/or I environmental monitoring identified by the Land Use Census pursuant to l Specification 3.12.2. j

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The Semiannual Radioactive Effluent Release Reports shall also include the j following: an explanation as to why the inoperability of liquid or gaseous  !

effluent monitoring instrumentation was not corrected within the time specified j in Specification 3.3.3.10 or 3.3.3.11, respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Specification 3.11.1.4 or 3.11.2.6, respectively. 1 MONTHLY OPERATING REPORTS 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later 'i than the 15th of each month following the calendar month covered by the report.

RADIAL PEAKING FACTOR LIMIT REPORT 6'S 1.9 The F y limit for RATED THERMAL POWER (F ) shall b ovided to tne Re, --21 Administrator of tne Regional Office of the ,C with a cocy to the Directo , Nuclear Reactor Regulation, Attentio hief, Core Performance Branch, U.S. Nu e Regulatory Commission, Wa i gton, D.C. 20555, for all core planes contain1. ' nk "D" control r and all unrodded core planes and the plot of predicted (F q .. Re.

vc 1al Core Height with the limit envelope at least 60 days prior to e e cyc tial criticality ualess otherwise approved by the Commiss4 oy letter. In ition, in the event that the limit l should change requi '.g a new submittal or an ed_ submittal to the Radial Peaking Factor oit Report, it will be submitted u s prior to the date the limit .d become effective unless otherwise approve the Commiss' RTP by le r. Any information needed to support F will be by re -

• xy and need not be included in this report.

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ADMINISTRATIVE CONTROLS 6.9.1.9 PEAKING FACTOR LIMIT REPORT The W(2) Functions for RAOC and Base Load operation and the value for APL"O (as required) shall be established for each reload core and implemented prior to use.

The methodology used to generate the W(z) functions for RAOC and Base Load Operation and the value,for APL ND shall be those previously reviewed and ap-proved by the NRC*. If changes to these methods are deemed necessary they will be evaluated in accordance with 10 CFR 50.59 and submitted to the NRC for re-view and approval prior to their use if the change is determined to involve an unreviewed safety question or if such a change would require amendment of pre-viously submitted documentation.

A report containing the W(z) functions for ROAC and Base Load operation and the value for APL"U (as required) shall be provided to the NRC document con-trol desk with copies to the regional administrator and the resident inspector within 30 days of their implementation.

ND Any information needed to support W(z), W(z)BL and APL will be by request from the NRC and need not be' included in this report. .

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