ML18039A562

Rev 0 to TVA-COLR-BF3C9, Bfnp Unit 3,Cycle 9 Colr.

ML18039A562
Person / Time
Site:	Browns Ferry
Issue date:	09/17/1998
From:	Bruce A, Keys T, Riley E TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18039A561	List: ML18039A560 ML18039A562
References
TVA-COLR-BF3C9, TVA-COLR-BF3C9-R, TVA-COLR-BF3C9-R00, NUDOCS 9810140182
Download: ML18039A562 (42)

Text

TVA Nuclear Fuel TVA-COLR-BF3C9 Core Operating Limits Repor Revision 0, Page I Browns Ferry Nuclear Plant Vnit 3, Cycle 9 CORE OPERATING LIMITSREPORT (COLR)

TENNESSEE VALLEYAUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By: /

Earl E. Riley,. Engineering Specialist BWR Fuel Engineering Verified By: Date: 't IC Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering 7f'pproved By: Date:

T. A. Keys, nager BWR Fuel Engineering Reviewed By:

eactor Engineering Supervisor Reviewed By:

PORC Chairman Revision 0 (9/17/98) Initial Release for New Cycle Pages Affected: All 98iOi40i82 98i005 PDR ADQCK 05000296 P PDR

it TVA Nuclear Fuel Core Operating'Limits Rep rt t TVA-COLR-BF3C9 Revision 0, Page 2 Revision Log Revision Date ~Descri tion Affected Pa es 0 9/17/98 Initial Release, for New Cycle All

Ik I

TVANuclear Fuel Core. Operating Limits Report t TVA-COLR-BF3C9 Revision 0, Page 3

1. INTRODUCTION This Core Operating Limits Report for Browns Ferry Unit 3, Cycle 9 is prepared in accordance with the requirements. of Browns Ferry Technical Specification 5.6.5. The core operating limits presented here were developed using NRC-approved methods (References 1 and 2). Results from the reload analyses for Browns Ferry Unit 3, Cycle 9 are documented in Reference 3.

The following core operating limits are included in this-report:

a. Average Planar Linear Heat Generation Rate.(APLHGR) Limit (Technical Specifications 3.2.1 and 3.7.5)

b. Linear Heat Generation Rate (LHGR) Limit (Technical Specification 3.2.3)

c. Minimum Critical Power Ratio Operating Limit (OLMCPR)

(Technical Specifications 3.2.2, 3.3.4.1, and 3.7.5) d.. Average Power Range Monitor (APRM) Flow Biased Rod Block Trip Setting (Technical Requirements Manual Section 5.3.1 and Table 3.3.4-1)

e. Rod Block Monitor (RBM) Trip Setpoints and Operability (Technical Specification Table 3.3.2.1-1)

f. Shutdown Margin (SDM) L'imit (Technical 'Specification 3.1.1)

TVANuclear Fuel Core Operating Limits Report-t TVA-COLR-BF3C9 Revision 0, Page 4

2. APLHGR LIMIT(TECHNICAL SPECIFICATIONS 3.2.1 AND 3.7.5)

The APLHGR limits for full power and flow conditions for each, type of;fuel as a function of exposure are shown in Figures 1-6. The APLHGR limits for the GE7B, GE11 and GE13 assemblies, are for the most limiting lattice (excluding natural uranium) at each exposure:point. The specific values for each lattice are given in Reference 4.

These APLHGR limits are adjusted for off-rated power and'. flow conditions using. the ARTS factors, MAPFAC(P) and MAPFAC(F). The reduced, power factor, MAPFAC(P),

is given in Figure 7. Similarly, adjustments for reduced flow operation are performed using the MAPFAC(F) corrections given in Figure 8. Both. factors are multipliers used to reduce the standard APLHGR limit. The most:limiting power-adjusted or flow-adjusted value is taken as the APLHGR operating limit.for the off-rated condition.

The APLHGR limits in figures 1-6 are applicable for both. Turbine Bypass In-Service and Out-Of-Service. The off-rated power and flow corrections in figures 7 and.8 bound both Turbine: Bypass In-Service and Out-Of-Service operation. No corrections are required to the APLHGR limits for TBOOS for either rated or off-rated operation.

Il TVA,Nuclear Fuel TVA-COLR-BF3C9 Core Operating Limits Report Revision 0,, Page 5

3. LHGR LIMIT(TECHNICAL SPECIFICATION 3.2.3)

The LHGR limit for unit 3 cycle 9 is fuel type dependent, as shown below:

Fuel Type LHGR L'imit GE7B (BP8X8R) 13.4 kw/ft GE11 14.4 kw/ft GE13 14.4 kw/ft

0 II ff

TVANuclear Fuel Core Operating Limits Report t TVA-COLR-BF3C9 Revision 0, Page 6

4. OLMCPR (TECHNICAL SPECIFICATIONS 3.2.2, 3.3.4;1, AND 3.7.5)

a. The MCPR Operating Limit for rated power and flow conditions, OLMCPR(100),

is equal to the.,fuel type and exposure dependent limit shown in Figure 9. For cycle 9, only GE13.results are supplied since they bound all bundle types. The.,actual OLMCPR(100)'alue is dependent upon the scram time testing results, as described below:

Caw CB 7 =00 or whichever is greater where; 'C= 1.096 sec (analytical Option A scram time limit - based-on dropout time. for notch position 36) n I

• N 2

p + 1.65

• cz n

where; p = 0.830 sec (mean scram time used in transient analysis-based on dropout time for notch position.36) cr = 0.019'se'c (standard deviation of p)

N = Total:number-of active rods measured in Technical Specification Surveillance Requirement SR3.1.4.1 n = Number of:surveillance rod tests performed.to date in cycle

~; = .Scram. time'(dropout time) from fully withdrawn to notch position 36 for the:i~ rod

b. Option A OLMCPR limits ('C =1.0) shall be used prior to the determination of 'E in accordance with SR 3.1'.4.1.

c. For off-rated power and flow conditions, power-adjusted and flow-adjusted operating limits are determined from Figures 10.and 11', respectively. The most

'limiting:power-dependent or flow-dependent value is taken as the OLMCPR for the off-rated condition.

d. OLMCPR limits and off-rated corrections are provided for Recirculation Pump Trip out-of-service (RPTOOS) or'Turbine Bypass out-of-service (TBOOS) conditions. These-events are analyzed separately and the core-is not.analyzed for both. systems Out-Of-Service at the same time.

I' TVA Nuclear Fuel Core Operating Limits Report t TVA-COLR-BF3C9

.Revision 0, Page'7

5. A'PRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL REQUIREMENTS MANUALSECTION 5.3.1 AND TABLE 3;3.4-1)

The APRM Rod Block trip setting shall be:

SRB < (0.66W + 61-%) Allowable Value SRB < (0.66W + 59%) Nominal Trip Setpoint (NTSP) where:

SRB = Rod Block setting in percent of rated thermal power (3458 MWt)

W = Loop recirculation flow rate in percent of rated The APRM Rod Block trip;setting is clamped at a maximum allowable value of 115%

(corresponding to a NTSP of 113%).

If TVANuclear Fuel Core Operating Limits Rep rt t TVA-COLR-BF3C9 Revision 0, Page 8

6. ROD BLOCK MONITOR (RBM) TRIP SETPOINTS AND OPERABILITY (TECHNICAL SPECIFICATION TABLE 3.3.2.1-1)

The RBM trip setpoints and applicable power ranges shall be as follows:

RBM Trip Setpoint AHowable Value Nominal Trip Setpoint (AV) (NTSP)

LPSP 27% 25%

IPSP 62% 60%

HPSP 82% 80%

LTSP - unfiltered 118.7% 117.0%

- filtered 117.7% 116.0% (l),(2)

ITSP - unfiltered 113.7% 112.0%

- filtered 112.9% 111.2% (l).(2)

HTSP - unfiltered 108.7% 107.0%

- filtered 107.9% 106.2% (l).(2)

DTSP 90% 92%

Notes: (1) These setpoints are based upon a MCPR operating limit of 1.29 using a safety limit of 1.10. This is. consistent with a MCPR operating limit of 1.25 using a safety limit of 1.07, as reported in references 6, 7, and 8.

(2) The unfiltered setpoints are consistent with a nominal RBM filter setting of 0.0 seconds, (reference 8). The filtered setpoints are consistent with a nominal RBM filter setting < 0.5 seconds (reference 7).

The RBM setpoints in Technical Specification Table 3.3.2.1-1 are applicable when:

THERMALPOWER Applicable Notes from MCPR Table 3.3.2.1-1

) 27% and < 90% RATED < 1.75 (a) (b), (f), (h)

) 90% RATED < 1.44 Note: The given MCPR operating limits are adjusted to correspond to a MCPR safety limit of 1.10. The values shown correspond to operating limits of 1.70 and 1.40 given the original 1.07 MCPR safety limit used in reference 6.

TVA Nuclear Fuel TVA-COLR-BF3C9 Core Operating. Limits Re ort' Revision 0, Page 9

7. SHUTDOWN MARGIN (SDM) LIMIT (TECHNICAL SPECIFICATION 3.1.1)

The core shall be subcritical with the following-margin with the strongest OPERABLE control rod fully withdrawn and all other OPERABLE control rods fully inserted.

SDM ) 0.38% dk/k

TVA Nuclear. Fuel TVA-COLR-BF3C9 Core Operating Limits Report Revision 0, Page 10 S .. 'REFERENCES

1. NEDE-24011-P-A-13,,"General Electric Standard Application for Reactor Fuel", August

1996.

2. NEDE-24011-P-A-'13'-US, "General..Electric'Standard Application for Reactor Fuel (Supplement for United States)", August 1996.

3. J11-03329SRLR Rev. 0, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 3 Reload 8 Cycle 9",,July 1998.

4. J1.1'-03329MAPL Rev. 0, "Lattice-Dependent MAPL'HGR Report for Browns Ferry Nuclear'Plant Unit,3 Reload 8 Cycle'9", July 1998.

5..NEDC-32774P Rev. 1, "Safety Analyses for Browns Ferry Nuclear Plant Units 1, 2, and 3 Turbine Bypass and End-of-Cycle Recirculation Pump Trip Out-Of-Service", dated:

'September 1997.

6. NEDC-32433P,."Maximum Extended. Load Line-Limitand ARTS Improvement Program Analyses for.Browns Ferry Nuclear Plant, Unit,l, 2, and 3", dated April 1995.

7.'DE-28-'0990'Rev. 3 Supplement E, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL(NUMAC) - Power-Uprate Condition] for Tennessee Valley Authority Browns-Ferry Nuclear Plant", dated October 1997.

8. EDE-28-0990 Rev. 2 Supplement E, "PRNM;(APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL(NUMAC) - Power-Uprate Condition] for Tennessee Valley Authority Browns Ferry Nuclear Plant", dated October 1997.

9. GE Letter LB¹: 262-97-133, "Browns Ferry Nuclear Plant Rod Block Monitor Setpoint Clarification - GE Proprietary Information",:dated September 12, 1997.

[L32 970912.800]

o' 10;GE Letter JAB-T8019a, "Technical Specification Changes for Implementation Advanced Methods", dated June 4, 1998. [L32 980608 800];

Ik TVANuclear Fuel TVA-COLR-BF3C9 Core Operating Limits Rep rt Revision 0, Page ll Figure 1 APLHGR Limits for Bundle Type GE13-P9HTB386-12GZ (GE13) 15.00 .

14.00 13.00 12.00 UNACCEPTABLE OPERATION 11.00 10.00 9.00 .

8.00 E

7.00 ACCEPTABLE OPERAT ION 5.00 5.00 ~

4.00 ~

3.00 .

2.00 1.00 0.00 0 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWDIST)

Most Limiting Lattice for Each Exposure Point

, Average Planar LHGR Average Planar LHGR Average Planar LHGR Exposure Limit Exposure Limit Exposure Limit GWD/ST kw/ft GWD/ST kw/ft GWD/ST kw/ft 0.0 10.83 7.0 12.03 25.0 10.94 0.2 10.94 8.0 12.19 30.0 10.24 1.0 11.08 9.0 12.36 35.0 9.55 2.0 11.25 10.0 12.51 40.0 8.87 3.0 11.41 12.5 12.53 45.0 8.20 4.0 11.57 15.0 12.27 50.0 7.53 5.0 11.72 17.5 11.95 55.0 6.85 6.0 11.88 20.0 11;62 57.62 6.48 These values apply to both Turbine Bypass In<ervlce and Out-OfNervice.

0 4k TVA Nuclear Fuel TVA-COLR-BF3C9 Core Operating Limits Report Revision 0, Page 12 Figure 2 APLHGR Limits for Bundle Type GE13-P9HTB372-11GZ (GE13) 15.00 14.00 13.00'2.00 UNACCEPTABLE OPERATION 11.00 10.00 9.00 8.00 E

7.00 ACCEPT ABLE OPERAT ION

o. 6.00 5.00 4.00 .

3.00 2.00 1.00-0.00 0 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWD/ST)

Most Limiting Lattice for Each Exposure Point Average Planar LHGR Average Planar LHGR Average Planar LHGR Exposure Limit Exposure Limit Exposure Limit GWD/ST kwlft GWD/ST kwlft GWD/ST kwlft 0.0 10.71 7.0 12.10 25.0 11.08 0.2 10.77 8.0 12.26 30.0 10.33 1.0 10.89 9.0 12.36 35.0 9.61 2.0 11.06 10.0 12.50 40.0 8.92 3.0 11.25 12.5 12 73 45.0 8.26 4.0 11.44 15.0 12.66 50.0 7.61 5.0 11.65 17.5 12.26 55.0 6.95 6.0 11.87 20.0 11.87 57.79 6.58 These values apply to both Turbine Bypass In4ervice and Out-Of-service.

II TVA Nuclear Fuel: TVA-COLR-BF3C9 Core'Operating Limits Report Revision 0, Page 13 Figure 3 APLHGR Limits for Bundle Type GE11-P9HUB323-5G5.0/4G4.0 (GE11) 15 14 13.

12 UNACCEPTABLE 0 PERATION 10 ~

9' E

7 ACCEPTABLE OPERATION Co X

3 2'.

0 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWD/ST)

Most Limiting Lattice for Each Exposure Point Average Planar LHGR Average Planar LHGR Average Planar LHGR Exposure Limit Exposure Limit Exposure Limit GWD/ST kwlft GWD/ST kw/ft GWD/ST kwlft 0.0 10.41 7.0 12.21 25.0 r10.97 0.2 10.44 8.0 12.42 30.0 10.25 1.0 10.54 9.0 12.64 35.0 9.57 2.0 10.75 10.0 12.82 40.0 8.93 3.0 11.01 12.5 12.70 45.0 8.24 4.0 11.30 15.0 12.38 50.0 7.49 5.0 11.62 17.5 12.06 55.0 6.55 6.0 11.95 20.0 11.73 57.70 6.08 These values apply to both Turbine Bypass In4ervice and Out-Of-Service.

t TVANuclear Fuel Core Operating Limits Report t TVA-COLR-8F3C9 Revision 0, Page 14 Figure 4 APLHGR Limits for Bundle Type GE11-P9HUB323-8G4.0 (GE11) 15.00 14.00, 13.00 12.00 UNACCEPTABLE.OPERATION 11.00 10.00 9.00 8.00 E

7.00 ACCEPTABLE OPERATION C91

o. 6.00 5.00 4.00'.00 2.00-1.00 .

i0.00 0.0 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWD/STI Most Limiting Lattice, for Each Exposure Point Average Planar LHGR Average Planar LHGR Average Planar LHGR Exposure Limit Exposure Limit Exposure Limit GWD/ST kw/ft GWD/S kwlft GWD/ST kwlft 0.0. 10.81 7.0 12.38 25.0 .10.07 8.0 12.51 30.0 10.25 1.0'0.91 0.2 2.0 10.83 11.11 9.0 10.0 12.65 12.79 35;0 40.0 9.57 8.93 3.0 11.36 12.5 12.71 45.0 8.25 4.0 11.63 15.0 12.39 50.0 7.51 5.0 11.93 17.5 12.07 55.0 6.58 6.0 12.25 20.0 11.72 57.72 6.10 These values apply to both Turbine Bypass In4ervlce and Out-Of4ervice.

Ih TVA Nuclear Fuel TVA-COLR-BF3C9 Core Operating L'imits Report Revision 0, Page 15 Figure 5 APLHGR Limits for Bundle Type GE11-P9HUB325-14GZ (GE11)

'15.00 14.00 13.00 12.00 . UNACCEPTABL'E 0 P.ERATION 11.00 .

10.00 9.00 .

,8.00 E

7.00 .

ACCEPTABLE OPERATION 6.00 5.00 4.00 .

3.00; 1.00 ~

'0.00 .

0.0 10.0 '20.0 30.0 40.'0 50.0 Cycle Exposure (GWD/ST).

Most Limiting Lattice for Each Exposure Point Average Planar LHGR Average Planar L'HGR Average Planar LHGR Exposure L'imit Exposure Limit Exposure Limit GWD/ST kwlft GWD/ST kwlft GWD/ST . kw/ft 0.0 9.48 7.0 11.80 25.0 10.87 0.2 9.57 8.0 12.07 .30.0 10.18 1:0 9.79 9.0 12.23 35;0 9.52 2.0 10.08 10.0 12.37 40;0 8.88 3.0 10.38 12.5 12.36 45.0 8.24 4.0 10.71 15.0 12:13 50.0 7.60 5.0 11.06 17.5 11;90 55;0 6.81 6.0 11.44 20.0 11.59 57.27 6.41 These. values apply to both Turbine Bypass In4ervice and Out-Of4ervice.

TVANuclear'Fuel TVA-COLR-BF3C9 Core Operating Limits Report Revision'0, Page 16 Figure 6 APLHGR Limits for Bundle Type BPSDRB284L (GE7B) 15.0 14.0 UNACCEPTABLE OPERATION 13.0 12.0 11.0 10.0; 9.0 ~

8.0 ACCEP TABLE OPERATIO E.

tc 7.0 6.0 5.0 4.0; 3.0.

2.0 1.0; 0.0 .

0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 Cycle Exposure (GWD/ST)

Average Planar LHGR . Average Planar LHGR Average Planar LHGR Exposure L'imit Exposure Limit Exposure Limit GWD/ST kw/ff GWD/ST kw/ft GWD/ST kw/ft 0.2 1.1 2 15.0 12.0 35.0 10.1 1.0 ,

.113 20.0 11.9 40.0 9.4 5;0 11.8 25.0 11.3 45.0 8.8 10.0 12.0 30.0 10.8 These. values apply to both Turbine Bypass In4ervice and Out-OfZervice.

0 TVA Nuclear Fuel TVA-COLR-BF3C9 Core Operating Limits'Report Revision 0, Page 17 Figure 7 Power Dependent MAPLHGR Factor - MAPFAC(P) 1.2 0.8 <<50% Core Flow O,

o. '0.6 0.4 I

> 50%'Core Flow 0.2 .

l I

I l

0 10 20 30 40 50 60 70 80 90 100 Power (% Rated) iMAPLHGR(P) = MAPFAC(P) x MAPLHGRstd For For 25% > P:

MAPLHGRstd = Standard MAPLHGR Limits 25% < P < 30%:

NO THERMAL'IMITSMONITORING REQUIRED MAPFAC(P) = 0.60+ 0.005(P-30%) For ( 50% CORE FLOW

MAPFAC(P) = 0.46+ 0.005(P-30%) Fol' 50% CORE FLOW For 30% < P MAPFAC(P) = 1.0 +,0.005224(P-100%)

These values bound both Turbine Bypass In-Service and Out-Of-Service

1 C

TVA Nuclear Fuel TVA-COLR-BF3C9 Core Operating Limits Report Revision 0, Page 18 Figure S Flow Dependent MAPLHGR Factor - MAPFAC(F)

I I MAXFLOW s 102.5Yo 0.9 0.8 O

0.7 MAX FLOW > 107/o F

'0.6-0.5 0.4-30 40 50 60 70 80 90 Flow (%'Rated)

'ore MAPLHGR(F) = MAPFAC(F) x MAPLHGRstd MAPLHGRstd = Standard MAPLHGR Limits MAPFAC(F) = MINIMUM(1'.0, Af

• Wc /100+ Bf)

Wc ='%ated'Core Flow Af and Bf are Constants Given Below:

Maximum Core Flow Af Bf.

% Rated) 102.5 '0.6784 0.4861 107.0. 0.6758 0.4574 These values bound both Turbine Bypass In-Service and Out-Of-Service.

The 102.5%.maximum flow line is used for operation up to 100% rated flow.

The 107% maximum flow line is used for. operation up to 105% rated flow (ICF).

4l Ik TVA Nuclear Fuel Core Operating Limits"Report t TVA-COLR-BF3C9 Revision 0, Page 19 Figure 9 MCPR Operating Limit for All Bundle Types 1.44 1.43 1.42 o 141 RPTOOS IL 1.4 C) 1.39 TBOOS I 1.38 E 1.37 1.36 c) 1.35 .

1.34 1.33 1.32 Turblno Bypass and Roclrculatlon Pump Trip In<orvtco 1.31 1.3 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1

'Option B Option A Tau (q)

'Exposure Range . Out-Of-Service Option A Option B Tao=1.0 Tau=0.0 BOC9 to EOC9 na 1.34 1 1.31 BOC9 to EOC9 Turbine B ass TBOOS 1.38 1.35 BOC9 to EOC9 Recirculation Pum Tri RPTOOS 1.43 1.35 Notes

1. Use this value prior to performing scram time testing per SR 3.1.4.1.

2. Either Turbine Bypass or Recirculation Pump Trip may be Out-Of-Service.'he core, is not analyzed for both TBOOS and RPTOOS at the same time.

II TVA Nuclear Fuel TVA-COLR-BF3C9 Core Operating Limits Rep rt Revision 0, Page 20 Figure 10 Power Dependent MCPR(P) Limits 3.2

>50)C FLOW (TBOOS) a 2.8 J2 '

ei 4 re rn 2.6 A,

a'0 2.4 0 g O 550)c FLOw (TBOOS) a'v 2.2 ~ >50% FLOW

)L'L (Equipment In-Sencce t IL R PTOOS)

CI r0 ae c50)I FLOW

~

(Equi pmeni ln-Service pg-CL 1 8 5 RPTOOS) 0A CL 0 1.6 1.4 re ce 1.2 0 10 20 30- 40 50 60 70 80 90 100 Rower (% Rated)

'OPERATING LIMITMCPR P) = K *OLMCPR 100)

For P< 25%: NO THERMALLIMITS MONITORING.REQUIRED For 25% < P < Pbypass: (Pbypass = 30%)

Kp = [Kbyp + 0.02(30%-P)]/OLMCPR(100)

Turbine B ass and RPT In-Service or RPT Out-Of-Service RPTOOS Kbyp =1;97 For < 50% CORE FLOW Kbyp=2.21 'For > 50% CORE FLOW Turbine'B ass Out-Of&ervice TBOOS Kbyp=2.01 For < 50% CORE FLOW Kbyp = 3.01,,For > 50% CORE FLOW- 'or 30% <'P <45% Kp = 1.28+ 0.01340(45%-P)

For 45% < P<60%  :,Kp = 1.15+ 0.00867(60%-P)

'For 60% < P ,: Kp = 1.00+ 0.00375(100%-P)

Note: Either Turbine Bypass;or Recirculation Pump Trip may be Out-Of-Service.

The core is not analyzed for. both TBOOS and RPTOOS at the same time.

0 il ~0

~ Ik

TVA Nuclear Fuel TVA-COLR-BF3C9 Core Operating Limits Report evision 0, Page 21 (Final)

Figure 11 Flow Dependent MCPR Operating Limit - MCPR(F) 1.7 1.6 1.5 EJ 1.4 MAXFLOW ~ 107%

MhX FLOW ~ 102.511 1.3 1.2 30 40 '50 60 70 80 90 Coro Flow (% Rated)

For Wc < 40%  : MCPR(F) = (Af'Wc/100+'Bf)"[1+0.0032(40-Wc)]

For Wc .> 40%  : MCPR(F) = MAX(1.23, Af*Wc/100+ Bf)

Wc = % Rated Core Flow Af and Bf are Constants Given Below:

Maximum Core Flow

% Rated) 102.5  %.587 1.701 107.0  %.603 1.745 These values bound both Turbine Bypass In4ervice and Out-OfZervice.

These values bound both Recirculation'Pump Trip In4ervlce and Out-Of<ervlce Either Turbine Bypass or,Recirculation Pump Trip may be Out-OfZervlce.

The core is,not analyzed for a combination of TBOOS and RPTOOS.

The 102.5% maximum flow line is used for operation up to 100% rated flow.

The 107% maximum flow line, is used for operation up to 105% rated flow (ICF).

0 gl Il~

h8 '0