ML18039A419

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Rev 2 to TVA-COLR-BF3C8, BFN Unit 3,Cycle 8 Colr
ML18039A419
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-BF3C8, TVA-COLR-BF3C8-R02, TVA-COLR-BF3C8-R2, NUDOCS 9807080145
Download: ML18039A419 (29)
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Text

ENCLOSURE 2

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 3 CORE OPERATING LIMITS REPORT (COLR), REVISION 2 FOR CYCLE 8 OPERATION (SEE ATTACHED) qa07080i45 9806~0 PDR ADQCK 05000260 PDR P

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 2, Page 1

Browns Ferry Nuclear Plant Unit 3, Cycle 8 CORE OPERATING LIMITSREPORT (COLR)

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

r'arl E. Riley, Engineering Specialist BWR Fuel Engineering Date:

S -Zl-~P Verified By:

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

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

ea tor Engineering Supervisor Date:

+8'g'eviewed By:

PORC Chairman Date:

Revision 2 (5/21/98)

Revise Coefficients for Tau Calculation Pages Affected:

1, 2, 4, 6

TVANuclear Fuel Core Operating Limits Report TVA-COLR-8F3CS Revision 2, Page 2 Revision Log Revision Date 0

2/6/97.

1 4/17/98

~Descri rien Initial Release Revise references and add MAPLHGR Data to accommodate fuel loading modifications during the mid-cycle 8 outage Affected Pa es All 1-3, 6, 15, 16-18 (re-number only) 5/21/98 Revise Tau Calculation (ref. BFN PER no. 98-005651-000) 1, 2, 4, 6

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 2, Page 3

1. INTRODUCTION This Core Operating Limits Report for Browns Ferry Unit 3, Cycle 8 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 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)

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.l.c, Table 3.2.C, and Specification 3.5.L) e.

Rod Block Monitor (RBM) Upscale (Flow Bias) Trip Setting and Clipped Value (Technical Specification Table 3.2.C)

2. APLHGR LIMIT(TECHNICALSPECIFICATION 3.5.I)

The APLHGR limit for each type of fuel 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 5.

e'

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3CS Revision 2, Page 4

3. LHGR LIMIT(TECHNICALSPECIFICATION 3.5.J)

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

~Fuel T e

LHGR Limit P8X8R/GE7B GE11 13.4 kw/ft 14.4 kw/ft

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

The OLMCPR is equal to the fuel type and exposure dependent MCPR limit at rated flow and rated power shown in Figures 1-2 multiplied by the Kf shown in Figure 3, where; Save ZB Z = 0.0 or 2=,

whichever is greater.

ZA ZB Z~ = 0.90 sec (Specification 3.3.C. 1 scram time limitto 20%

insertion from fullywithdrawn )

ZB = 0.694 + 1.65 (0.016) n ng T.

i=l Save n

Reference 7 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 ofactive rods measured in Specification 4.3.C. 1 at BOC.

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

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3CS Revision 2, Page 5

c. For the performance of Surveillance Requirement4.5.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 5 (0.58W + 57%)

where:

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

W = Loop recirculation flow rate in percent of rated 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 + 46%)

where:

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

W = Loop recirculation flow rate in percent of rated RBM upscale flow-biased setpoint clipped at 112 percent rated reactor power.

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 2, 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. J11-02967SRLR Rev. 0, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 3 Reload 7 Cycle 8", January 1997.
4. Jl 1-02967MAPL Rev. 0, "Lattice-Dependent MAPLHGRReport for Browns Ferry Nuclear Plant Unit 3 Reload 7 Cycle 8", January 1997.
5. 24A5178AA Rev. 1, "Lattice-Dependent MAPLHGRReport for Browns Ferry Nuclear Plant Unit 3 Reload 6 Cycle 7", August 1995.
6. GE letter LB¹262-98-042, "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.
7. 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.

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 2, Page 7 Table 1

APLHGR Limits for Bundle Type GE11-P9HUB323-565.0/464.0 (GE11)

Most Limiting Lattice 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 57.7 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

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 2, Page 8 Table 2 APLHGR Limits 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

'7.72 APLHGR Limit kw/ft 10.81 10.83 10.91 11.11 11.36 11.63 11.93 12.25 12.38 12.51 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

'VANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 2, Page 9 Table 3 APLHGR Limits for Bundle Type GE11-P9HUB325-14GZ (GE11)

Most Limiting Lattice 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 57.27 APLHGR 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 12.37 12.36 12.13 11.90 11.59 10.87 10.18 9.52 8.88 8.24 7.60 6.81 6.41

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3CS Revision 2, Page 10 Table 4 APLHGR Limits for Bundle Type PSDRB283 (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 11.2 11.2 11.7 12.0 12.0 11.9 11.3 10.8 10.4 10.0 9.5

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3CS Revision 2, Page 11 Table 5 APLHGR Limits for Bundle Type P8DRB314 (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 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

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 2, Page 12 Table 6 APLHGR Limits for Bundle Type PSDRB299 (P8X8R)

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 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 10.65 9.36

0

'VANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 2, Page 13 Table 7 APLHGR Limits for Bundle Type BP8DRB284L (GE7B or BP8X8R)

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 11.2 11.3 11.8 12.0 12.0 11.9 11.3 10.8 10.1 9.4 8.8

0

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 2, Page 14 Table 8 APLHGR Limits for Bundle Type P8DRB284Z (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 APLHGR Limit kw/ft 11.2 11.2 11.7 12.0 12.0 11.9 11.3 10.8 10.4 9.9 9.5

I

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3CS Revision 2, Page 15 Table 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 25.0 30.0 35.0 40.0 APLHGR Limit kw/ft 11.6 11.6 12.1 12.1 12.1 11.9 11.3 10.7 10.2 9.6

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3CS Revision 2, Page 16 Figure I MCPR Operating Limitfor P8X8R &, GE7B (BP8XSR) 1,38 1.37 1,35 I

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

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 2, Page 17 Figure 2 MCPR Operating Limitfor GE11 1.38 1.37 1.35 1.34 H

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0.0 0.1 0.2 0.3 0.4 0.5 0.8 0.7 0.8 0.9 1.0 Option a Option A Ex osure Ran e

BOC8 to EOC8 0 tion A au=1.0 1.35

  • 0 tion B Tau=0.0 1.32
  • Use this value at BOC8 prior to performing scram time testing.

'VANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 2, Page 18 (Final) 1.4 Figure 3 GEXL-Plus Kf Curve OLMCPR Flow Corrections None 1.3 117.0%

112.0%

107.0%

102.5 %

1.020 30 40 50 60 70 Total Core Flow (% rated) 80 90 100 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 = Percent of Rated Core Flow, and A = constant which depends on the Flow Control Mode and the Scoop Tube Setpoint as noted below.

Flow Control Mode MANUAL MANUAL MANUAL Scop Tube Set oint 102.5 %

107.0 %

112.0 %

1.3308 1.3528 1.3793 MANUAL 117.0 %

1.4035 AUTOMATIC N/A 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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