ML18039A417

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Rev 1 to TVA-COLR-BF2C10, BFN Unit 2,Cycle 10 Colr.
ML18039A417
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 05/28/1998
From: Bruce A, Keys T, Riley E
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18039A416 List:
References
TVA-COLR-BF2C10, TVA-COLR-BF2C10-R01, TVA-COLR-BF2C10-R1, NUDOCS 9807080143
Download: ML18039A417 (39)
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Text

ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 2 CORE OPERAT ING LIMITS REPORT (COLR) I REVIS ION 1 FOR CYCLE 10 OPERATION (SEE ATTACHED) 9807080i4$ 980630 05000260 PDR ADQCK P ,

PDR eY

TlANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 1, Page 1 Browns Ferry Nuclear Plant Unit 2, Cycle 10 CORE OPERATING LIMITSREPORT (COLR)

TENNESSEE VALLEYAUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By: Date: <- ~1-8 Earl E. Riley, En eering Specialist BWR Fuel Engineering Verified By: Date:

Alan L, Bruce, Nuclear Engineer BWR Fuel Engineering Approved By:

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

actor Engineering Supervisor Reviewed By:

P RC Chairman Revision 1 (5/21/98) Revise Coefficients for Tau Calculation Pages Affected: 1, 2, 6, 9

0 TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 1, Page 2 Revision Log Revision Date ~Descri tion Affected Pa es 0 9/25/97 Initial Release All 5/21/98 Revise Tau Calculation (ref. BFN PER I, 2, 6, 9 no. 98-005651-000)

TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 1, Page 3

1. INTRODUCTION This Core Operating Limits Report for Browns Ferry Unit 2, Cycle 10 is prepared in accordance with the requirements of Browns Ferry Technical Specification 6.9.1.7. 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 2, Cycle 10 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 Specification 3.5.I)
b. Linear Heat Generation Rate (LHGR) Limit (Technical Specification 3.5.J)
c. Minimum Critical Power Ratio Operating Limit (OLMCPR)

(Technical Specification 3.5.K/4.5.K)

d. Average Power Range Monitor (APRM) Flow Biased Rod Block Trip Setting (Technical Specification 2.1.A.1.c and Table 3.2.C)
e. Rod Block Monitor (RBM) Trip Setpoints (Technical Specification Table 3.2.C)

TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 1, Page 4

2. APLHGR LIMIT(TECHNICAL SPECIFICATION 3.5.I)

The APLHGR limits for full power and flow conditions for each type of fuel as a function of exposure are shown in Figures 1-8. The APLHGR limits for the GE9B, 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 9. Similarly, adjustments for reduced flow operation are performed using the MAPFAC(F) corrections given in Figure 10. Both factors are multipliers used to reduce the standard APLHGR limit. The most limiting power-adjusted or fiow-adjusted value is taken as the APLHGR operating limit for the off-rated condition.

TVANuclear Fuel TVA-COLR-BF2C10

~ Core Operating Limits Report Revision 1, Page 5

3. LHGR LIMIT(TECHNICAL SPECIFICATION 3.5.J)

The LHGR limit for unit 2 cycle 10 is fuel type dependent, as shown below:

Fuel Type LHGR:Limit GE7B (BP8X8R) 13.4 kw/ft GE9B (GE8X8NB) 14.4 kw/ft GE11 14.4 kw/ft GE13 14.4 kw/ft

TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 1, Page 6

4. OLMCPR (TECHNICAL SPECIFICATION 3.5.K/4.5.K)
a. The MCPR Operating Limit for rated power and fiow conditions, OLMCPR(100),

is equal to the fuel type and exposure dependent limit shown in Figures 11, 12, 13, and 14. The actual OLMCPR(100) value is dependent upon the scram time testing results, as described below:

Save ZB 2 =00 or whichever is greater.

Z~ = 0.90 sec (Specification 3.3.C.1 scram time limit to 20%

insertion from fully withdrawn )

I Zs = 0.694 + 1.65 N 2 (0.016) Reference 10 n

n g

i=1 ri Save n

where; n = Number of surveillance rod tests performed to date in cycle (including BOC test).

Zi = Scram time to 20% insertion from fully withdrawn of the i rod.

N = Total number of active rods measured in Specification 4.3.C. 1 at BOC.

b. For theperformanceof Surveillance Requirement 4.5.K.2.a (prior to initial scram time measurements for the cycle),

'C = 1.0

c. For the performance of Surveillance Requirement 4.5.K.2.b, 'C shall be determined in accordance with 4.a above.
d. For off-rated power and flow conditions, power-adjusted and flow-adjusted operating limits are determined from Figures 15 and 16, respectively. The most limiting power-dependent or flow-dependent value is taken as the OLMCPR for the off-rated condition.

TVA Nuclear Fuel TVA-COLR-BF2C10

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Core Operating Limits Report Revision 1, Page 7

5. APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL SPECIFICATION 2.1.A.l.c AND TABLE 3.2.C)

The APRM Rod Block trip setting shall be:

SRB < (0.66W+ 66%) Allowable Value SRB < (0.66W + 64%) Nominal Trip Setpoint (NTSP) where:

SRB = Rod Block setting in percent of rated thermal power (3293 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%).

0 0

TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 1, Page 8

6. ROD BLOCK MONITOR (RBM) TRIP SETPOINTS (TECHNICAL SPECIFICATION TABLE 3.2.C)

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

RBM ~Trip Setpoint- Allowable:Value Nominal Trip Setpoint (AV)' '(NTSP)

LPSP 27% 25%

IPSP 62% 60%

HPSP 82% 80%

LTSP - unfiltered 121.7% 120.0%

- filtered 120.7% 119.0% (l) (2)

ITSP - unfiltered 116.7% 115.0%

- filtered 115.7% 114.0% (l) (2)

HTSP - unfiltered 111.7% 110.0%

- filtered (>) (2) 110.9% 109.2%

DTSP 90% 92%

Notes: (1) These setpoints are based upon a MCPR operating limit of 1.34 using a safety limit of 1.10. This is consistent with a MCPR operating limit of 1.30 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).

Ci TVA Nuclear Fuel TVA-COLR-BF2CI 0

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Core Operating Limits Report Revision 1, Page 9

7. 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. J11-03144SRLR Rev. 1, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 2 Reload 9 Cycle 10", September 1997.
4. Jl 1-03144MAPL Rev. 0, "Lattice-Dependent MAPLHGR Report for Browns Ferry Nuclear Plant Unit 2 Reload 9 Cycle 10", August 1997.
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 Limit and ARTS Improvement Program Analyses for Browns Ferry Nuclear Plant Unit 1, 2, and 3", dated April 1995.

7.. EDE-28-0990 Rev. 3 Supplement F, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL(NUMAC) - Current Rated Condition] for Tennessee Valley Authority Browns Ferry Nuclear Plant", dated Sept. 1997,

8. EDE-28-0990 Rev. 2 Supplement F, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL(NUMAC) - Current Rated Condition] for Tennessee Valley Authority Browns Ferry Nuclear Plant", dated Sept. 1997.
9. GE Letter LBP: 262-97-133, "Browns Ferry Nuclear Plant Rod Block Monitor Setpoint Clarification - GE Proprietary Information", dated September 12, 1997.

[L32 970912 800]

10.GE letter JSC-005-086 to US NRC, "Revised Supplementary Information Regarding Amendment 11 to GE Licensing Topical Report NEDE-24011-P-A", dated January 16, 1986.

T VA Nuclear Fuel TVA-COLR-BF2C10

~ Core Operating Limits Report Revision 1, Page 10 Figure 1 APLHGR Limits for Bundle Type GE13-P9HTB384-12G4.0 (GE13) 15.

14.

13

12. UNACCEPTABLE OPERATION 10 g g 8

E 3 ACCEPTABLE OPERATION rc 7-to 5

0 ~

0 10.0 20.0 30.0 40.0 50.0 Cycto Exposure (GWD/ST1 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 10.09 7.0 '.

r 11.71 25.0 10.6 0.2 10.15 8.0 11.95 30.0 9.99 1.0 '0.31 9.0 12.16 35.0 9.39 2.0 10.52 10.0 12.28 40.0 8.76 3.0 10.75 12.5 12.16 45.0 8.11 4.0 10.99 15.0 11.88 50.0 7.44 5.0 11.25 17.5 11.56 55.0 6.74 6.0 11.48 20.0 11.24 55.98 6.60

TVA Nuclear Fuel TVA-COLR-BF2C1 0 Core Operating Limits Report Revision I, Page 11 Figure 2 APLHGR Limits for Bundle Type GE11-P9HUB366-12G4.0 (GE11) 15 UNACCEPTABLE OP ERATION 10

~P 8

E 7

ACCEPTABLE OPERATION U

X 0

0.0 10.0 20.0 30.0 40.0 50.0 Cyclo Exposure (GWD/ST)

Most Limiting Lattice for Each Exposure Point Average'Planar."

>> Exposure'imit GWD/ST

"'~

'. 'w/ft

'L'HGR;-. ='Average

=", = -

Planar,

.Exposure:

GWD/ST

'LHGR:.: Average Planar

""Limit':'"Exp'osure kw/ft GWD/ST

'imit

-. LHGR kw/ft 11.39 25.0 10.51 0.0 0.2 1.0

'.62 I 9.55 9.80 7.0 8.0 9.0

~

l 11.67 11.81 30.0 35.0 9.84 9.19 3.0, 2.0 4.0 )

10.05 10.32 10.58 10.0 12.5 150 11.95 11.92 11.72 40.0 45.0 50.0 8.55 7.91 7.26 5.0 10.84 17.5 11.48 55.0 6.59 6.0 11.11 20.0 11.20 56.17 6.42

TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 1, Page 12 Figure 3 APLHGR Limits for Bundle Type GE11-P9HUB367-14GZ (GE11) 15 14 13 ~

12. UNACCEPTABLE OPERATION 10 ~

8 E

7 ACCEPTABLE OPERATION U

x 5

0 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 ':: -, LHGR ..". Average, Planar~ LHGR

Exposure,'-:= ";- Limit',-".;.:="'Exposure' '=Limit . . Exposure Limit GWD/ST ' - kw/ft '~". ' GWD/ST -

kw/ft 'WD/ST, kw/ft

'1.31

~

0.0 I 9.18 7.0 25.0 10.51 0.2 I 9.27 80 "

1167 30.0 9.84 10 I 945 9.0 11.81 35.0 9.19 2.0 3 9.72 10.0 ~ 11.95 40.0 8.55 30 1000 12.5 i 11.92 45.0 7.91 40 I

i 1030 15.0:, 11.72 50.0 7.26 5.0 '0.62 17.5 11.48 55.0 6.59 6.0 10.95 20.0 11.20 56.17 6.42

TVANuclear Fuel TVA-COLR-BF2CI 0 Core Operating Limits Report Revision 1, Page 13 Figure 4 APLHGR Limits for Bundle Type GE9B-P8DWB319-9GZ (GE8X8NB) 15 14 13 12 UNACCEPTABLE OPERATION 8

E

7. ACCEPTABLE OPERATION U

5 0

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 L'HGR'; 'Average Planar, LHGR Ayera'ge Planar LHGR Exposure Limit . 'xposure, Limit

. Exposure Limit GWD/ST, kw/ft, GWD/ST , kw/ft GWD/ST kwlft 00 s 1164 7.0 12.49 35.0 10.41 12.65 45.0 8.81 02 1.0 I

'1.77 11.68 8.0 90 '277 I

51.2 5.91 20 I 1188 10.0 12.86 3.0 " 12.01 12.5 ~

12.86 4.0 12.12 15.0 12.62 5.0 12.22 20.0 . 12.06 6.0 12.32 25.0 11.47

TVA Nuclear Fuel TVA-COLR-BF2C10

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Core Operating Limits Report Revision 1, Page 14 Figure 5 APLHGR Limits for Bundle Type GE9B-PSDWB325-10GZ (GE8X8NB) 15 13.

12 ~ UNACCEPTABLE OPERATIO g

8 E

7 ACCEPTABLE OPERATION to 8

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

Most Limiting Lattice Average Planar ..

.",, LHGR for Each Exposure Point Average Planar LHGR Average Planar LHGR

'.. ', 'wlft Exposure Limit -, Exposure Limit -Exposure Limit GWD/ST kw/ft GWD/ST GWD'/ST kwlft

'0.97 7.0 12.23 35.0 10.12 0.0

'235

~i 0.2 I 11.00 80 45.0 8.60 1 0 I; 11 11 9.0 12.46 50.27 5.92 2.0 $ 11.31 10.0 12.58 3.0 I 11.54 12.5 12:58 4.0  ! 11.79 15.0 12.35 5.0 II 11.97 20.0 11.86 6.0 12.10 25.0 11.33

TVA Nuclear Fuel TVA-COLR-BF2C10

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Core Operating Limits Report Revision 1, Page 15 Figure 6 APLHGR Limits for Bundle Type GE9B-PSDWB326-7GZ (GE8X8NB) 15 UNACCEPTABLE OPERATION C!

8.

E 7

ACCEPTABLE OPERATION U

x 0

0.0 10.0 20.0 30.0 40.0 50.0 Cyclo Exposure (GWD/ST)

Most Limiting Lattice for Each Exposure Point Average Planar 'LHGR 'Average",Planar.'HGR 'verage Planar LHGR

~

Limit .'xposure"

'Exposure Limit, Exposure Limit

, kwlft 'WD/ST,

. GWD/ST kw/ft GWD/ST kw/ft 0.0 I 11.45 7.0 i 12.31 35.0 10.15 0.2 i 11.47 8.0 I 12.41 45.0 8.72 1.0 I 11 55 9.0 '2.51 50.49 5.93 2.0 "'1.70 100 I 1263 3.0 '1.87 12.5 '. 12.64 4.0 15.0 12.41 50 '213 I 12.01 20.0 '1.91 6.0 12.22 25.0 11.35

'I TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 1, Page 16 Figure 7 APLHGR Limits for Bundle Type BPSDRB301L (BP8X8R) 15 14 UNACCEPTABLE OPERATION 13.

12 10 ~

8 ACCEPTABLE OP E RATION E

IL 7 t9 2 ~

0 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 cyclo Exposure (GWD/ST)

Average Pla'nar 'LHGR iAv'erage Planar'.. "."LHGR" " "Average Planar LHGR Exp'osure GWD/ST,. '

.Limit kw/ff

'xpo'sure'imit

.';., 'WD/ST -

'w/ft Expo'sure GWD/ST Limit kwlft 0.0 11.32 7.0 I 11.98 350 '082 0.2 11.33 8.0 I 12.03 43.52 9.17 1.0 11.40 9.0 '12.11 2.0 11.50 100

'219 3.0 4 0 '173 i 11.61 12.5, 15.0 ~

12.34 12.47 50 l 1186 20.0 12.58 6.0 11.93 25.0 12.03

TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 1, Page 17 Figure S APLHGR Limits for Bundle Type BPSDRB299 (BP8X8R) 15 14 UNACCEPTABLE OPERATION 13 ~

12.

10.

8 E

3 ACCEPTABLE OPE RATION IL' (a

3 0

0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 Exposure (GWD/ST) 'yclo Average'Planar" "

LHGR Average, Planar 'HGR Average Planar LHGR Ex'pos'ure" Limit Exposure "

Limit Exposure . Limit GWD/ST '- kw'Ift GWD/ST kw/ft GWD/ST kwlft

'0.71 0.0 02 1.0 I 1075 10.86 8.0; 7.0 9.0, I 11.78 11.95 12.09 35.0 42.13 10.65 9.36 2.0 11.01 10.0 12.20 3.0 11.19 12.5 '2.37 4.0 '1.35 15.0 12.47 5.0 11.47 20.0 12.37 6.0 11.62 25.0 11.77

TVA Nuclear Fuel TVA-COLR-BF2CI 0

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Core Operating Limits Report Revision 1, Page 18 Figure 9 Power Dependent MAPIHGR Factor - MAPFAC(P) 1.2 0.8 < 50% Core Flow g+ 0.6 ~

0.4 .

I I

~ 50% Cor e Flow 0.2 I I

I 10 20 30 40 50 60 70 80 90 100 Power (% Rated)

MAPLHGR(P) = MAPFAC(P) x MAPLHGRstd MAPLHGRstd =, Standard MAPLHGR Limits For 25% )P 'NOTHERMALLIMITSMONITORINGREQUIRED For 25% < P< 30%; MAPFAC(P) 0.60+0005(P 30%) For c 50% CORE FLOW

'APFAC(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

TVA Nuclear Fuel TVA-COLR-BF2CI 0

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Core Operating Limits Report Revision l, Page 19 Figure 10 Flow Dependent MAPLHGR Factor - MAPFAC(F)

MAXFLOW ~ 102.5%

0.9 .

0.8 O

0.7 MAXFLOW i 107%

0.6 0.5 .

0.4 .

30 40 50 60 70 80 90 100 Coro Flow (% Rated)

MAPLHGR(F) = MAPFAC(F) x MAPLHGRstd MAPLHGRstd = Standard MAPLHGR Limits MAPFAC(F) = MINIMUM(1.0,Af

  • Wc /100+ Bf)

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

Maximum, =

Coie Flow .

(% 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).

0 TVA Nuclear Fuel TVA-COLR-BF2C10

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Core Operating Limits Report Revision 1, Page 20 Figure 11 MCPR Operating Limit for GE13 1.43 1.42 .

1.41 .

CP O

f Turbin e Bypass 0 ut-Of4erv Ice o 1.39 B 1.36 4 1.37.

B Turbine Bypass InNervlce O 1.36.

oc g 1.35.

1.33 0 0.1 0.2 0.3 0.4 0.5 0.6 , 0.7 0.6 0.9 1 Option B Option A Tau (q)

Exposure Range Out-'Of-Service " "Option A Option'B'au=0.0

  • 4 Tau=,1.'0 BOC10 to EOC10 na 1.37 1 1.34 BOC10 to EOC10 Turbine B pass 1.41 1.38 Notes
1. Use this value at BOC10 prior to performing scram time testing.

~,

TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 1, Page 21 Figure 12 MCPR Operating Limit for GE11 1.43 ~

1.42 1.41-CI f

O 14.

oI 1.39 5 1.38 Tu rbine Byp ass Out&1Nefvlce

= 1.37 CL

< 1.36 m 1.35.

Turbine Bypass In<ervice 1.33 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" Rang'e  ;, Out-Of;Serytce'.,-; , -.Option'A Option B Tau=1.0 ,

Ta'u=0.0 BOC10 to EOC10 na 1.35 1 1.34 BOC10 to EOC10 Turbine B ass 1.39 1.36 Notes

1. Use this value at BOC10 prior to performing scram time testing.

TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 1, Page 22 Figure 13 MCPR Operating Limit for GE9B (GESXSNB) 1.39 ~

1.38 C)

CI 1.37 O

o 1.36.

urblne Byp ass Out-0 f<ervlce E

g 1.35.

1.34 o

O Turb!no Bypass In<orvico 1.33 1.32 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Option A Option B Tau (q)

'" Out-Of-Service, .,'ption'A . 'Option B

,Exposure"'Range.'OC10

'a 'Tau=1.0 Tau=0.0 to EOC10 1.34 1 1.34 BOC10 to EOC10 Turbine B pass 1.36 1.34 Notes

1. Use this value at BOC10 prior to performing scram time testing.

0 TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 1, Page 23 Figure 14 MCPR Operating Limit for GE7B (BPSXSR) 1.39 1.38 CI ID 1.37 O

I 1.36 E

g 1.35.

L Turbine Bypass In<ervice & Out&f<ervice 1.34 O

1.33 1.32 0 01 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 E

Tau=1.0 Tau=0.0 BOC10 to EOC10 na 1.34 1 1.34 BOC10 to EOC10 Turbine B pass 1.34 1.34 Notes

1. Use this value at BOC10 prior to performing scram time testing.

TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 1, Page 24 Figure 15 Power Dependent MCPR(P) Limits 3.2 I

>505'LOW tTBOOS)

CO Ol OS CL 2.8 0 th 0

Ih IO 2.6 A 2.4 0

~V CL 2.2 550% FL0W p BOOS)

YL 0 0 1.8 pg CL 5505'LOw C X CL A 1.6 0 0

'U Cl 1.4 lO 1.2 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)

OPERATING LIMITMCPR P = K 'LMCPR 100 For P < 25% ~

NO THERMAL LIMITS MONITORING REQUIRED For 25% < P < Pbypass (Pbypass = 30%)

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

Turbine B ass In&ervice Kbyp =1.97 For < 50% CORE FLOW

=

Kbyp 2.21 For > 50% CORE FLOW Turbine B ass Out-Of-Service Kbyp = 2.01 For < 50% CORE FLOW Kbyp = 3.01 For > 50% CORE FLOW For 30% < P<45% Kp = 1.28+ 0.01340(45%-P)

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

For 60% < P Kp = 1.00+ 0.00375(1 00%-P)

TVA Nuclear Fuel TVA-COLR-BF2CI 0

~ Core Operating Limits Report Revision 1, Page 25 (Final)

Figure 16 Flow Dependent MCPR Operating Limit - MCPR(F) 1.7 1.6 1.4 .

MAXFLOW ~ 1 07'A MAXFLOW s 102.5%

1.2 30 40 50 60 70 80 90 100 Coro Flow I% Ratod)

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 Afand Bf are Constants Given Below:

"." Maximum" i ~... I

. 'Coro Flow;,"'. ='k .'f.",

%'Rated)','02.5

%.587 1.701 107.0  %.603 1.745 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).

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