rev 0 to 'river bend station,cycle 7,colr,feb 1996.' · . _ . . .. | - page 1 of19 rbs...

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RIVER BEND STATION, CYCLE 7

CORE OPERATING LIMITS REPORT (COLR)

.

| February 1996;

1

/2M288PREPARED BY: Date:.

Respo'nsible Engineeri

REVIEWED BY: 4 4/$N M 2/> >- Date: /2////96Review Engineer

/3I&!bAPPROVED BY: / 8d Date:Manager - Safety & EngineeringAnalysis

,

'APPROVED DY: Date:

Director, EngineeringRiver Bend Nuclear Station

jD b/

lAPPROVED BY: Date: / I* - .

'

Facilities Review Commihee1'

River Bend Nuclear Station

.

:

,

9602210145 960209ADOCK0500g8DR


Revision 0

INTRODUCTION AND SUMMARY

This report provides the values of the AVERAGE PLANAR LINEAR HEATGENERATION RATE (APLHGR) limits, the core flow dependentMINIMUM CRITICAL POWER RATIO (MCPR) limits, MCPR , the thermalfpower dependent MCPR limits MCPR , the LINEAR HEAT GENERATION i

pRATE (LHGR) limits, APRM Gain and setpoint information, and theREACTOR PROTECTION SYSTEM (RPS) response time for APRMthermal time constant for River Bend Station, Cycle 7 as required byTechnical Specifications. Technical Specifications require these values ,

be determined using NRC-approved methodology and are established i

such that all applicable limits of the plant safety analysis are met. ,

Control Rods

The River Bend core utilizes both GE original equipment and ABB CR-82M bo.ttom entry cruciform control rods. These Control Rod designs are ,

discussed in more detail in reference 8.

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TECHNICAL SPECIFICATION 3.2.1

POWER DISTRIBUTION LIMITS

AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

The limiting APLHGR value for the most limiting lattice (excluding naturaluranium) of each fuel type as a function of AVERAGE PLANAREXPOSURE is given in Figures 1,2,3,4,5,6 and 7. These values weredetermined with the SAFE /REFLOOD LOCA methodology described inGESTAR-il (Reference 1). Core location by fuel type is provided inFigure 11 and is the reference core loading pattern in reference 3. Thesefigures are used if alternate calculations are required. The limits of thesefigures shall be reduced to a value of 0.84 times the two recirculation loopoperation limit when in single loop operation (Reference 4).

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MINIMUM CRITICAL POWER RATIO (MCPR)

The MCPR limits for use in Technical Specification 3.2.2 for flowdependent MCPR (MCPR ) (reference 5, 9), power dependent MCPRf(MCPR )(reference 5) are shown in Figures 8,9 and 10. These valuespwere determined with the GEMINI methodology and GEXL-PLUS criticalpower ratio correlation described in GESTAR-Il (Reference 1) and areconsistent with a Safety Limit MCPR of 1.07.

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LINEAR HEAT GENERATION RATE (LHGR).

The LHGR limits for use in Technical Specification 3.2.3 are 14.4 kw/ft forGE8x8EB and GE11 (Reference 6). The GE8x8EB fuel consists of fueltypes: GE88-P8 SOB 333-10GZ-120M-4WR-150-T, GE8B-P8SQB334-10GZ-120M-4WR-150-T, GE8B-P8SQB334-10GZ2-120M-4WR-150-Tand GE88-P8SQB334-11GZ-120M-4WR-150-T. The GE11 (9x9) fuelconsists of GE11-P9SUB354-14GZ-120T-146-T, GE11-P9SUB354-13GZ-120T-146-T and GE11-P9SUB353-10GZ-120T-146-T. Core location by

;

fuel type is provided in Figure 11.>

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RBS CYCLE 7 COLRRevision 0

TECHNICAL SPECIFICATION TABLE 3.3.1.1-1'

.

The simulated thermal power time constant for use in TechnicalSpecification Table 3.3.1.1-1, SR 3.3.1.1.14, is (Reference 7):

6 i O.6 seconds.

The maximum simulated thermal power time constant for use in Technical-

Specification surveillance Table 3.3.1.1-1, SR 3.3.1.1.14 is:

6.6 seconds;

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! TECHNICAL SPECIFICATION 3.2.4


Averaae Power Ranae Monitor (APRM) Gain and Setooints

The APRM Gain and Setpoint information below was transferred fromTechnical Specifications as part of implementation of Improved Technical:Specifications in October of 1995. For APRM flow biased simulatedthermal power-high scram trip setpoints and/or the flow biased neutronflux-upscale control rod block trip setpoint adjustment for the condition T <1.0, the following relationships apply:

Two Recirculation Loop Operation

Trio Setooint Allowable Value

S s (0.66W + 48%)T S s (0.66W + 51%)TSns s (0.66W + 42%)T Saa s (0.66W + 45%)T

Single Recirculation Loop Operation

Trio Setooint Allowable Value'

S s (0.66W + 42.7%)T S s (0.66W + 45.7%)T' -

Sns s (0.66W + 36.7%)T Saa s (0.66W + 39.7%)T

|

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where: S and Sas are in percent of rated thermal power,

W = Loop recirculation flow as a percentage of the looprecirculation flow which produces a rated core flow of 84.5million Ibs/hr,

T is defined in Technical Specification Basis section B 3.2.4

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REFERENCES

1) NEDE-24011-P-A, " General Electric Standard Application for ReactorFuel,"(latest approved version).

1 2) Letter, C.O. Thomas to J.S. Charnley, " Acceptance for Referencing ofLicensing Topical Report," NEDE-24011-P-A-6, Amendment 10, GeneralElectric Standard Application for Reload Fuel, May 28,1985.

3) 24A5188, Rev. O " Supplemental Reload Licensing Report for River BendStation Reload 6/ Cycle 7" November 1995.

4) " Single-Loop Operation Analysis for River Bend Station, Unit 1," NEDO-31441, May 1987,

5) Letter, Hoa Hoang to Gary Scronce, " Additional Specifications for RiverBend Station MCPR(P) and MCPR(F) Limits for Cycle 7 Application"1 ENOM-2395. December 7,1995.

6) FC# 818R46," RIVER BEND RELOAD 6 DESIGN EXPOSURE CYCLESUMMARY" June 1995.

7) Letter, R.E. Kingston to G. W. Scronce, " Time Constant Values forSimulated Thermal Power Monitor" GFP-1032 November 30,1995.

8) RBS USAR Section 4.1

9) Letter, Hoa Hoang to Gary Scronce, " River Bend Station MCPR(F) Limitsfor Cycle 7 Application" 1ENOM-2195. December 6,1995.

.

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FIGURE 1 MAXIMUM AVERAGE PLANAR LINEAR HEATGENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR

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FIGURE 8 OPERATING LIMIT MCPR (MCPRe) VERSUS CORE FLOW

1.8 .

i1 , i i i . I i i !i i ; i

! i 8 ! i ( ! I

' ! r i ! ;

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6 . i i i . 1 .

I i i e i ! l !

! ! ! I i i i i i r i r i

"MCPRe = MCPRr(30) 4- -i i

1.7 -.; For; W < 30% n__,;, ,

|'iy ; j' MCPRe = [1.848-0.71*W/100]*[1.128-0.32*W/100]~

' ! s ! ! For; 30 2 W < 40%-

|. . I's ! MCPRe = [1.848-0.71*W/100] b_, -

!' ||is! For; W 2 40% and MCPRe > OLMCPR b-' '

- ,-

i, -,

1.6 ',, ,' MCPRr = 1.22 (GE8),1.28 (GE11) eRated OLMCPR $

,

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20 40 60 80 100 120

CORE FLOW (W), % OF RATED CORE FLOW

.

J

. _ _ _ _ _ _ _ _

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Revision 0i

FIGURE 9 OPERATING LIMIT MCPR (MCPR,)VERSUS THERMAL POWER FOR EXPOSURES

LESS THAN EOC-3350 mwd /ST1.8 i . : i i . i i i i

i i ! i ! I i i i i ! i !

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l i ii ! $ . ! i

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i i i i i i (40,1.71)_

i ' - i i ! + 4 - !>', 4 i , i i !!,

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1.7- |' |,

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i ! II ! ii i i f i i

--t -- i .

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I I ! ! I i ! ! i '

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THERMAL POWER, % OF RATED THERMAL POWER

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__-_-_-_ _ ________ _ __ . _ ___

of 19 )RBS CYCLE 7 COLR

Revision 01

I

FIGURE 10 OPERATING LIMIT MCPR (MCPR,) i

VERSUS THERMAL POWER FOR EXPOSURES i

lGREATER THAN OR EQUAL TO EOC-3350 mwd /ST !

1.8 , , , ,

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!

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! . i i ! ! i ! i 3 ! '

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j i + i t . , i i i !

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Di! i Iiiii i ii i I ! i'

1

20 40 60 80 100 120

THERMAL POWER, % OF RATED THERMAL POWER

_ _ ._. _ , . . . _ . . . _ _ _ _ . _ _ . . _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ . . . - _ _ _

Pago 19 of 19i

RBS CYCLE 7 COLR l

Revision 0

FIGURE 11 REFERENCE CORE LOADING PATTERN

l

56- @@@@@@@@

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| ||: M M M M M M M M M M M M M E |1

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:: 'MMMMMMMMMMM":

! ': "HMMMMMMMM5! : "M M M. M..M..M M": 2 m

| | | | | | | || e n o a o is n n a ir a n n n n a u n .s o .e u u is4 i ii7i

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rev 0 to 'river bend station,cycle 7,colr,feb 1996.' · . _ . . .. | - page 1 of19 rbs...

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