ML18039A343

Rev 1 to COLR Cycle 8 for Browns Ferry Nuclear Plant Unit 3

ML18039A343
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Site:	Browns Ferry
Issue date:	04/17/1998
From:	Bruce A, Keys T, Riley E TENNESSEE VALLEY AUTHORITY
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ML18039A341	List: ML18039A340 ML18039A343
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ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 3 CORE OPERATING LIMITS REPORT (COLR), REVISION 1 FOR CYCLE 8 OPERATION (SEE ATTACHED) 98052i0107 9805ii PDR noaCK 0500mve P

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TVAa~lUclear FUel Core Operating'Lir Report J33 980417 806 Browns Ferry Nuclear Plant Unit 3, Cycle 8 TVA COLR-BF3C8 Revision i, Page i QA RE't:ORD CORE OPERATING LIMITSREPORT (COLR)

TENNESSEE VALLEYAUTHOMTY Nuclear Fuel Division BWR Fuel Engineering Department

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'repared By:

Earl E. Riley, Engineer' Specialist BWR Fuel Engineering Verified By:

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

'T. A. Keys, M ger BWR Fuel Engineering Date:

z Date:

tt tatt'u I

IL W N CC

~r5o Cl Dat" '//7 I'L Ih u' la e o Reviewed By:

Reviewed eactor Engineering Supervisor PORC Cha Date: 4 ~7 ~E Jt

~g/g Revision 1,(4/17/98)

Mid-cycle 8 Outage Fuel Loading Modifications Pages Affected:

1-3,6,15-18

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TVANuclear Fuel

.@ore Operating Limit ort TVA-COLR-BF3CS Revision 1, Page 2 Revision Iog Revision Date 0

2/6/97 1

4/17/98 D~eecri cion InitialRelease Revise references and add MAPLHGR Data to accommodate fuel loading modifications during the mid-cycle 8 outage Affected P.a es 1-3, 6, 15, 16-18 (re-number only)

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TVANuclear Fuel i:om Operating L'imttort TVA-COLR-BF3CS Revision l, Page 3..

INTRODUCTION This Core Operating Limits Report for Browns Ferry Unit 3, Cycle 8 is prepared in accordancet 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 3, Cycle 8 are documented:in Reference 3 and'6.

The following:core operating limits.are'included in.this report:

a. Average Planar Linear Heat Generation Rate (APLHGR) Limit (Technical Specification 3.5.I)'.

Linear Heat Generation Rate (LHGR) Limit (Technical'pecification 3.5.J)

c. Minimum Critical Power Ratio Operating Limit(OLMCPR)

(Technical Specification 3.5.'K/4.5.K) a

d. Average Power Range Monitor (APRM) Flow Biased Rod Block Trip Setting (Technical Specification 2.1.A.l.c, Table 3;2.C, and Specificati'on 3.5.L)

e. Rod Block Monitor (RBM) Upscale (Flow Bias) Tr'ip Setting and Clipped Value (Technical Specification Table 3.2.C)

2. APLHGR.LIMIT(TECHNICALSPECIFICATION 3.5.I)

The APLHGR limitfor each type offuel as a function of exposure is shown in Tables 1-9. The APLHGR limits for the GE11 assemblies are. for the most limiting lattice at each exposure point. The specific values. for each lattice are given in References 4 and i5

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TVANuclear Fuel Core Operating Limi ort TVA-COLR-BF3CS Revision l, Page 4

3. LHGRLIMIT(TECHNICALSPECIFICATION 3.5.J)

The LHGR limitfor unit 3 cycle 8 is fuel type dependent, as shown below:

~Fuel T.

e LHGR Limit PSXSR/GE7B GE11 13.4 kw/ft

- 1'4.4 kw/ft

4. OLMCPR (TECHNICALSPECIFICATION 3.5.K/4.5.K) a.

The OLMCPR is equal to the fuel type and exposure dependent MCPR limitat rated flow and rated power shown in:Figures 1-2 multiplied by the Kfshown in Figure,3, where; Z = 0.0 or whichever is greater.

Zi = 0.90 sec (Specification 3.3.C.1 scram time limitto 20%

insertion from fullywithdrawn )

i Zi = 0.710 + 1.65 (0.053)

.N 2

n ng Zi Save i=i n

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

Zi = Scram time to 20% insertion from fullywithdrawn ofthe ith rod.

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

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

'7 =1.0

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TVANuclear Fuel Core Operating Limit~ort TVA-COLR-BF3CS Revision 1, Page 5

c. For the performance ofSurveillance Requirement 4.5.K.2.b,

'6 shall be determined in accordance with 4.a above.

.5. APRM FLOW BIASED ROD BLOCKTRIP SETTING (TECHNICAL SPECIFICATION 2.1.A.1.c, TABLE3.2.C, AND SPECIFICATION 3.5.L).

The APRM-Rod Block trip setting shall be:

SRB g (0 58W + 57%)

where:

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

W = Loop recirculation flowrate in percent ofrated Note:

Under certain conditions, the APRM Rod Block setting must be adjusted'by FRP/CMFLPD.

See Technical Specification 3;5;L.

6. RBM UPSCALE'(FLOW BIAS) TRIP SETTING AND CLIPPED VALUE (TECHNICALSPECIFICATION TABLE3.2.C)

The RBM Upscale trip setting shall be:

< (0.66W+ 460')

where:

Trip.level setting is'in percent of rated thermal power (3293 MWt)

W = Loop recirculation flowrate in percent ofrated RBM upscale flow-biased setpoint,clipped at 112 percent. rated reactor power.

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TVANuclear Fuel Core Operating Limi ort TVA-COLR-BHCS Revision l, Page 6

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. J11-02967SRL'R Rev. 0, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 3 Reload 7 Cycle 8",.January 1997.

4. J11-02967MAPL Rev. 0, "Lattice-Dependent MAPLHGRReport for Browns Ferry Nuclear Plant Unit 3 Reload 7'Cycle 8", January 1997; 5: 24A5178AA Rev. 1, "Lattice-Dependent.MAPLHGR,Report for Browns Ferry Nuclear Plant Unit 3 Reload'6 Cycle 7", August 1995.

"6. GE letter'LB8262-98-042, "Browns Ferry Nuclear Plant Unit 3 Cycle 8 Safety Evaluation ofMid-Cycle Modified.Core Loading on SRLR Applicability-GE Proprietary Information", dated April 16, 1998.

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TVANuclear Fuel Core Operating Limi ort TVA-COLR-BF3CS Revision 1, Page 7 Table 1

APLHGR Limits for Bundle Type GE11-P9HUB323-5G5.0/4G4.0 (GE11)

Most LimitingLattice for Each Exposure Point Average Planar. Exposure

~GWD/ST 0.0 0.2.

1.0 2.0 3.0 4.0 5.0'.0 7.0 8.0 9.0 10.0 12.5 15.0 17.5 20.0 25.0 30.0 35.0 40.0 45.0 50;0 55.0 57.7 APLHGR Limit kw/ft 10.41 10.44 10.54 10.75 11.01 11.30 11;62 11'.95 12.21 12.42 12.64 12.82 12;70 12.38 12.06 11.73 10.97 10.25 9.57 8.93 8.24 7.49 6.55 6.08

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TVANuclear, Fuel'ore Operating Limi ort TVA-COLR-BF3C8 Revision l, Page 8 Table 2 APLHGRLimits for Bundle Type GE11-P9HUB323-8G4.0 (GE11)

Most LimitingLattice for Each Exposure Point Average Planar Exposure

~GWD/ST 0.0 0.2 1'.0 2.0 3.0 4;0 5.0 6.0 7.0 8.0 9.0 10;0 12.5 15.0 17.5 20.0 25:0 30.0 35.0 40.0 45.0 50;0 55.0 57.72 APLHGR Limit kw/ft 10.81 10.83 10.91 11.11 11.36 11'.63 11.93 12.25 12.38 12.5 1:

12.65 12.79 12.71 12.39 12.07 11.72 10.97 10.25 9:57 8.93 8.25 7.51 6.58 6.10

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TVANuclear Fuel Core Operating. Limi ort TVA-COLR-BF3CS Revision I, Page 9 Table 3 APLHGR Limits for Bundle Type GE11-P9HUB325-14GZ (GE11)

Most LimitingLattice for Each Exposure Point Average Planar Exposure

~GWD/ST 0.0 0.2 1.0 2.0 3.0'.0 5.'0 6.0 7.0 8.0 9.0 10.0 12.5 15.0 17.5 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 57.27'PLHGR Limit kw/ft 9.48 9.57 9.79 10.08 10.38 10.71 11.06 11.44 11.80 12.07 12.23'2.37-12.36 12.13 11.90 11.59 10.87 10.18 9.52 8.88

'8.24 7.60 6.81 6.41

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TVANuclear Fuel Core Operating Limit ort TVA-COLR-BF3CS Revision 1, Page 10 Table 4 APLHGR Limits for Bundle Type P8DRB283 (LTA)

(P8X8R)

Average Planar-Exposure

~GWD/ST 0.2 1.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 APLHGRLimit kw/ft 1'1.2 11.2 11.7 12.0 12.0 11.9 11.3 10.8 10.4 10.0 9.5

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TVANuclear Fuel Core Operating Limi ort J

TVA-COLR-BF3CS Revision I, Page l 1 Table 5 APLHGR Limits for Bundle Type PSDRB314 (LTA)

(P8XSR)

Average Planar Exposure

~GWD/ST 0.2 1.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 APLHGR Limit kw/ft 10.6 10.7 11.3 11.7 11.5 11.2 10.6 10.1 9.7 9.3 8.8

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TVANuclear Fuel

'Core Operating Limi ort TVA-COLR-BF3C8 Revision 1, Page 12 Table 6 APLHGR Limits for. Bundle Type P8DRB299 (P8X8R)

Average Planar Exposure

~GWD/ST 0.0 0.2 1.0'.0 3.0 4;0 5.0 6.0 7;0 8'.0 9.0 10.0 12.5 15.0 20.0 25.0 35.0 42.13 APLHGR Limit kw/ft 10.71 10.'75 10.86 11.01 11.19 11.35 11'.47 11;62 11.78 11.95 12.09 12.20 12.37 12.47 12;37 11.77

'0.65 9.36

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TVANuclear Fuel

'Core Operating Limit ort TVA-COLR-BF3CS Revision 1, Page 13 Table 7 APLHGR Limits for Bundle Type BP8DRB284L (GE7B or BPSX8R)

.Average Planar Exposure

~GWD/ST 0.2 1.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40;0 45.0 APLHGRLimit kw/ft 11.2 11.3 11.8 12.0 12.0 11.9 11.3 10.8 10.1 9.4 8.8

TVANuclear, Fuel

'Core Operating Limit ort TVA-COLR-BF3CS Revision'1, Page 14 Table 3 APLHGR Limits for Bundle Type PSDRB284Z (P8X8R)

Average Planar Exposure

~GWD/ST 0.2 1.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 APLHGRLimit kw/ft 11.2 11.2 11.7 12.0 12.0 1'1.9 11.3 10.8 10.4 9.9 9.5

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TVANuclear Fuel

'Core Operating Limi ort TVA-COLR-BF3CS Revision 1, Page 15'able 9

APLHGR Limits for Bundle Type P8DRB265L (P8X8R)

Average Planar Exposure

.~GWD/ST 0.2 1.0 5.0 10.0 15;0 20.0'5.0 30.0, 35.0 40.0 APLHGRLimit kw/ft 11.6 11.6 12.1 12.1 12.1 11.9'1.3 10.7 10.2 9.6

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TVANuclear Fuel

'Core Operating Limit ort TVA-COLR-BF3CS Revision 1, Page 16 FlgUI'l 1

MCPR Operating Limitfor PSXSR X GE7B (BPSXSR) 1E87 1.35 1.83 IR 1.82 1E81 I

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0.0 0.1 Option B 0.2 0.8 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Option A E~R BOC8 to EOC8 0 tion A Tau=1.0 1.33

• 0 tion B Tan=0.0 1.30

• Use this value at BOC8 prior to performing scram time testing.

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TVANuclear Fuel

'Core Operating Limi ort TVA'-COLR-BF3CS Revision 1, Page 17 Flgllre 2 MCPR Operating Limitfor GE11 1.37 g

1.33 1.32 1.31 1.29 I

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I 1.28 0.0 0.1 Option B 0.2 0.3 0.4 0.5 0.8 0.7 0.8 0.9 Option A 1.0 H~R BOC8 to EOC8 0 tion A Tau=1.0 1.35

• 0 tionB Tan=0.0 1.32

~ Use this value at BOC8 prior to performing scram-time testing.

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TVANuclear Fuel

~ Core Operating Limi~ort TVA-COLR-BF3C8 Revision I, Page 18 (Final) 1.4 Figure 3 GEXL-Plus Kf Curve OLMCPR Flow Corrections 1.3 117.0%

112.0%

107.0%

102.5%

1 e2 1.020 30 40 50 60 70 80 90 100 Total,Core Flow (% rated):

For 40%< WT,< 100%,

Kf = MAX,[1.0, A-0.00441*WT,]

WT< 40%,

Kf = [A - 0.00441+WT] + [1.0+0.0032+(40-WT)]

WT' 100%. 'Kf = 1;0 where:

WT = PercentofRated

CoreFlow, and A =.constant wluch depends on the Flow Control Mode and the Scoop

'Tube Setpoint as noted below.

Flow Control Mode Scop Tube Set 1oint, A

MANUAL.

MANUAL'ANUAL'ANUAL AUTOMATIC 102:5 %

107.0 %

112;0 %

117.0 %

N/A 1.3308 1.3528 1.3793 1.4035 1.4410 Note:

Flow Corrections are given for P8x8R and'BP8x8R bundles. These corrections are conservative when compared to GE11 flowcorrections which do not have the additional correction'factor of

[1.0+ 0.0032*(40-WT)] below'40% flow.

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