ML20093G847

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Rev 0 to Brown Ferry Nuclear Plant Unit 3,COLR
ML20093G847
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 09/22/1995
From: Bruce A, Keys T, Riley E
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20093G842 List:
References
TVA-COLR-BF3C7, TVA-COLR-BF3C7-R, TVA-COLR-BF3C7-R00, NUDOCS 9510190261
Download: ML20093G847 (16)
v • d • e


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TVA Nuclear Fuel TVA-COLR-BF3C7 Core Operating Lt .3 Report Revision 0, Page 1

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Browns Ferry Nuclear Plant Unit 3, Cycle 7 I i

CORE OPERATING LIMITS REPORT (COLR)

TENNESSEE VALLEY AUTIIORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By: , [ 1/ Date: 9/te/95~

Earl E. Riley, Engineering Specialist BWR Fuel Engineering Verified By: b Alan L. Bruce, Nuclear Engineer Date: *//22/9f BWR Fuel Engineering Approved By: ~ J Date: k)

T. A. Keysglanager / /

BWR Fuel Engineering Reviewed By: NMb3b Date: 9[2Gk6 Reactor Engineering SuQor Reviewed By: _ M '

Date: 1/a9/95

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'[/PORC Chairmin d

9510190261 951013 PDR ADOCK 05000296 P PDR

'., TVA Nuclear Fuel TVA-COLR-BF3C7

.. Core Operating Li.. 3 Repon Revision 0, Page 2 l

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Revision Log 1

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TVA Nuclear Fuci TVA-COLR-BF3C7

., Core Operating Liu.4 Repon Revision 0, Page 3

1. INTRODUCTION This Core Operating Limits Report for Browns Ferry Unit 3, Cycle 7 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 7 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.' APRM Flow Biased Rod Block Trip Setting (Technical Specification 2.1.A.I.c, Table 3.2.C, and Specification 3.5.L)

e. RBM Upscale (Flow Bias) Trip Setting and Clipped Value

] (Technical Specification Table 3.2.C)

2. APLHGR LIMIT (TECHNICAL SPECIFICATION 3.5.I)

The APLHGR lir. lit for each type of fuel as a function of exposure is shown in Tables 1-7. The APLHGR limits for the Gell assemblies are for the most limiting lattice at each exposure point. The specific values for each lattice are given in Reference 4.

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.. .. Core Operating Lit 4 Repon Revision 0, Page 4

3. LIIGR LIMIT (TECIINICAL SPECIFICATION 3.5.J)

The LIIGR limit for unit 3 cycle 7 is fuel type dependent , as shown below:

Fuel Tyne LHGR Limit P8X8R/GE7B 13.4 kw/ft Gell 14.4 kw/ft

4. OLMCPR (TECHNICAL SPECIFICATION 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 Kr shown in Figure 3, where; T ~ Te T = 0.0 or T= , whichever is greater. '

D - Te t = 0.90 sec (Specification 3.3.C.1 scram time limit to 20%

insertion from fully withdrawn )

1 Te = 0.710 + 1.65 * (0.053)

.n.

n D

  1. =

Tave =

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

i I = Scram time to 20% insertion from fully withdrawn of the i th rod N = Tctal number of active rods measured in Specification 4.3.C.1 atBOC i

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

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T = 1.0 l I

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.. Core Operating Lit . 4 Report Revision 0, Page 5 I

c. For the performance of Surveillance Requirement 4.5.K.2.b, T shall be determined in accordance with 4.a above.
5. APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL SPECIFICATION 2.1. A.1.c, TABLE 3.2.C, AND SPECIFICATION 3.5.L)

The APRM Rod Block trip setting shall be:

SRB s (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 (TECIINICAL SPECIFICATION TABLE 3.2.C)

The RBM Upscale trip setting shall be:

s (0.66W + 43%)

where:

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

W = Loop recirculation flow rate in l

percent of rated l l

l RBM upscale flow-biased setpoint clipped at 109 percent rated reactor power.

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, . TVA Nuclear Fuel TVA-COLR BF3C7 Core Operating Lit .s Report Revision 0, Page 6

7. REFERENCES
1. NEDE-24011-P-A-10, " General Electric Standard Application for Reactor Fuel",

February 1991.

2. NEDE-24011-P-A-10-US, " General Electric Standard Application for Reactor Fuel", March 1991.
3. 24A5178 Rev.1, " Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 3 Reload 6 Cycle 7", August 1995.
4. 24A5178 AA Rev.1, " Lattice-Dependent MAPLHGR Report for Browns Ferry Nuclear Plant Unit 3 Reload 6 Cycle 7", August 1995.

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, . TVA Nuclear Fuel TVA-COLR-BF3C7 Core Operating Lit. s Report Revision 0. Page 7 Table 1 APLHGR Limits for Bundle Type GE11-P9 HUB 325-14GZ (Gell)

Most Limiting Lattice for Each Exposure Point Average Planar Exposure APLHGR Limit (GWD/ST) kw_/11 0.0 9.48 0.2 9.57 1.0 9.79 2.0 10.08 3.0 10.38 4.0 10.71 5.0 11.06 6.0 11.44 7.0 11.80 8.0 12.07 9.0 12.23 10.0 12.37 12.5 12.36 15.0 12.13 17.5 11.90 20.0 11.59 i 25.0 10.87 I 30.0 10.18 35.0 9.52 40.0 8.88 45.0 8.24 50.0 7.60 55.0 6.81 57.27 6.41 1

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TVA Nuclear Fuel TVA-COLR-BF3C7

,, Core Operating Liu..a Repon Revision 0, Page 8 Table 2 APLHGR Limits for Bundle Type P8DRB283 (LTA)

(P8X8R) l Average Planar Exposure APLHGR Limit (GWD/ST) kw/ft 0.2 11.2 1.0 11.2 5.0 11.7 10.0 12.0 15.0 12.0 20.0 11.9 25.0 11.3 30.0 10.8 l 35.0 10.4 '

40.0 10.0 45.0 9.5 t

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.. Core Operating Liu a Report Rcvision 0, Page 9 j 4

Table 3 APLHGR Limits for Bundle Type P8DRB314 (LTA)

(P8X8R)

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

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.. Core Operating Lit.s Report Revision 0. Page 10 Table 4 APLHGR Limits for Bundle Type P8DRB299 (P8X8R)

Average Planar Exposure APLHGR Limit (GWD/ST) }cyfft 0.0 10.71 0.2 10.75 1.0 10.86 2.0 11.01 3.0 11.19 4.0 11.35 5.0 11.47 6.0 11.62 7.0 11.78 8.0 11.95 9.0 12.09 10.0 12.20 12.5 12.37 15.0 12.47 20.0 12.37 25.0 11.77 l 35.0 10.65 l 42.13 9.36 i

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TVA Nuclear Fuel TVA-COLR BF3C7

. Core Operating Liu Report Revision 0, Page 1I Table 5 APLHGR Limits for Bundle Type BP8DRB284L (GE7B or BP8X8R)

Average Planar Exposure APLHGR Limit

' (GWD/ST) kw_El i

0.2 11.2 1.0 11.3

5.0 11.8 10.0 12.0 15.0 12.0 20.0 11.9 25.0 11.3 30.0 10.8 35.0 10.1 40.0 9.4 45.0 8.8 i

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. Core Operating Lit .a Report Revision 0, Page 12 4

Table 6 APLHGR Limits for Bundle Type P8DRB284Z (P8X8R)

Average Planar Exposure APLHGR Limit (GWD/ST) kw/ft 0.2 11.2 1.0 11.2 5.0 11.7 10.0 12.0 .

15.0 12.0 20.0 11.9 25.0 11.3 30.0 10.8 35.0 10.4 40.0 9.9 45.0 9.5 i

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, Core Operating Lii. s Report Revision 0, Page 13 1

Table 7 APLHGR Limits for Bundle Type P8DRB265L (P8X8R)

Average Planar Exposure APUiGR Limit (GWD/ST) kwjft 0.2 11.6 1.0 11.6 5.0 12.1 10.0 12.1 15.0 12,1 20.0 11.9 25.0 11.3 30.0 10.7 35.0 10.2 40.0 9.6

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TVA Nuc! car Fuel TVA-COLR-BF3C7

, Core Operating Lit.4 Repmt Revision 0, Page 14 Figure 1 MCPR Operating Limit for P8X8R & GE7B (BP8X8R) 1 30 i I

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e Exposure Ranee Option A (Tau =1.0) Option B (Tau =0.0)

BOC7 to EOC7 1.29

  • 1.27 4

Use this value at BOC7 prior to performing scram time testing.

  • TV4 Nuclear Fuel TVA-COLR-BF3C7 Core Operating Lii s Repon Revision 0, Page 19 Figure 2 MCPR Operating Limit for Gell 1 30 1 35 -- --

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  • Use this value at BOC7 prior to performing scram time testing.

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, TVA Nuclear Fuci TVA-COLR-BF3C7

. Core Operating Liu..s Report Revision 0, Page 16 (Final) ;

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Figure 3 GEXL-Plus Kf Curve OLMCPR Flow Corrections l 1.4 i

, Ncme -

117 0 %

1.3 -

182 0 %

107 0 %

102 s %

$21.2 -

1.1 -

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4 1.0 ' ' ' '

20 30 40 50 80 70 80 90 100 Total Core Flow (% rated)

For 40% < WT1100%, Kr = MAX [ 1.0, A - 0.00441*WT ]

WT1 40%, Kr = [A - 0.00441*WT ] * [1.0 + 0.0032*( 40 - WT )]

WT > 100 %, Kr = 1.0 where : WT = Percent of Rated Core Flow, and l A = constant which depends on the Flow Control Mode and the Scoop

. Tube Serpoint as noted below.

Flow Control Mode Scoop Tube SetDoint A MANUAL 10'2.5 % 1.3308 MANUAL 107.0 % 1.3528 MANUAL 112.0 % 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 GElI flow corrections which do not have the additional correction factor of

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

-r

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