ML18039A483

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Rev 3 to Unit 3 Cycle 8 Colr
ML18039A483
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 07/09/1998
From: Bruce A, Keys T, Riley E
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18039A481 List:
References
NUDOCS 9808210179
Download: ML18039A483 (35)
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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 3, 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:

Earl E. Riley, Engineering Specialist BWR Fuel Engineering Date:

<</~re~

Verified By:

Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering Date:

Approved By:

T. A. Keys, Ma ger BWR Fuel Engineering Reviewed By:

eactor Engineering Supervisor

'ate:

Reviewed By:

PORC Chairman Revision 3 (7/8/98) 98082iOi79 9808i7 PDR ADQCK 05000260 P

PDR Revise to Implement Improved Technical Specifications Pages Affected:

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 3, Page 2 Revision Log Revision Date 0

2/6/97 1

4/17/98

~Descri tion 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 7/8/98 Revise to Implement Improved Technical Specification Requirements - also formatting changes for consistency with unit 2 COLR All

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 3, 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 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 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 3.2.1 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 Specification 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.

APRM Setpoint Changes for MFLPD Greater Than the Fraction of Rated Power (Technical Specification 3.2.4)

f. Rod Block Monitor (RBM) Setpoints (Technical Specification Table 3.3.2.1-1 and Section 5.6.5) g.

Shutdown Margin (SDM) Limit (Technical Specification 3.1.1)

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Core Operating Limits Report TVA-COLR-BF3CS Revision 3, Page 4

2. APLHGR LIMIT(TECHNICALSPECIFICATIONS 3.2.1 AND3.7.5)

The APLHGR limit for each type of fuel as a function of exposure is shown in Figures 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.

The APLHGR limits in Figures 1-9 are applicable for both Turbine Bypass In-Service and Out-Of-Service. No corrections are required to the APLHGR limits for TBOOS.

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Core Operating Limits Report TVA-COLR-BF3CS Revision 3, Page 5

3. LHGR LIMIT(TECHNICALSPECIFICATION 3.2.3)

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

Fuel Type LHGR Limit P8X8R/GE7B (BP8X8R) 13.4 kw/ft GE11 14.4 kw/ft

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Core Operating Limits Report TVA-COLR-BF3C8 Revision 3, Page 6

4. OLMCPR (TECHNICALSPECIFICATIONS 3.2.2, 3.3.4.1, and 3.7.5) a.

The MCPR Operating Limit, OLMCPR, is equal to the fuel type and exposure dependent limitshown in Figures 10 8c 11 multiplied by the Kfgiven in Figure

12. The actual OLMCPR value obtained from Figures 10 8c 11 is dependent upon the scram time testing results, as described below:

'C = 0.0 or Cave CB whichever is greater where;

'C= 1.096 sec (analytical Option A scram time limit-based on dropout time for notch position 36) n ave i

N 2

p + 1.65

  • o
  • n where; p =

0.830 sec (mean scram time used in transient analysis-based on dropout time for notch position 36) o =

0.019 sec (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 'C in accordance with SR 3.1.4.1.

c.

OLMCPR limits 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.

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Core Operating Limits Report TVA-COLR-BF3C8 Revision 3, Page 7

5. APRM FLOW BIASED ROD BLOCKTRIP SETTING (TECHNICAL REQUIREMENTS MANUALSECTION 5.3.1 ANDTABLE3.3.4-1)

The APRM Rod Block trip setting shall be:

SRB (0.58W + 57%)

where:

W

= Rod Block setting in percent of rated thermal power

= Loop recirculation flow rate in percent of rated Note:

Under certain conditions, the APRM Rod Block setpoint must be adjusted by (FRP/MFLPD), in accordance with Technical Specification 3.2.4. See COLR section 6.

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Core Operating Limits Report TVA-COLR-BF3C8 Revision 3, Page 8

6. APRM SETPOINT CHANGES FOR MFLPD GREATER THANTHE FRACTION OF RATED POWER (TECHNICALSPECIFICATION 3.2.4)

Ifthe core Maximum Fraction of LimitingPower Density (MFLPD) is greater than the Fraction of Rated Power (FRP), adjust the following APRM setpoints (ifexitting LCO 3.2.4 by satisfying LCO requirement 3.2.4.b):

a)

APRM Flow Biased Simulated Thermal Power Scram setpoint - Function 2.b in Technical Specification Table 3.3.1.1-1.

b) APRM Flow Biased Rod Block Trip Setpoint - COLR Section 5.

This adjustment is performed by multiplying the unadjusted setpoint by the ratio of (FRP/MFLPD), as follows:

FRP SmJ = Sotuo*

wllere:

SAn]

= Adjusted APRM Scram or Rod Block Setpoint SORIG

= Unadjusted (original) APRM setpoints from Technical Specification Table 3.3.1.1-1 (Function 2.b) or COLR section 5

= Fraction of Rated Core Thermal Power (based on 3293 MWt)

MFLPD

= Core Maximum Fraction of LimitingPower Density

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3CS Revision 3, Page 9

7. ROD BLOCKMONITOR (RBM) SETPOINTS (TECHNICAL SPECIFICATION TABLE3.3.2.1-1 AND SECTION 5.6.5)

The RBM Upscale flow biased 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.

The Downscale setpoint shall have an allowable value of ) 3% rated reactor power.

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

THERMALPOWER'pplicable MCPR Notes from Table 3.3.2.1-1

> 90% RATED

( 1.44 (a)

) 29% and ( 90% RATED Note:

The given MCPR operating limits are adjusted to correspond to a MCPR safety limitof 1.10. The values shown correspond to operating limits of 1.70 and 1.40 given the original 1.07 MCPR safety limit.

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Core Operating Limits Report TVA-COLR-BF3C8 Revision 3, Page 10

8. SHUTDOWN MARGIN(SDM) LIMIT (TECHNICALSPECIFICATION 3.1.1)

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

SDM > 0.38% dk/k

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Core Operating Limits Report TVA-COLR-BF3C8 Revision 3, Page 11

9. 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. 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 MAPLHGRReport for Browns Ferry Nuclear Plant Unit 3 Reload 6 Cycle 7", August 1995.
6. GE letter LBP262-98-042, "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 JAB-T8019a, "Technical Specification Changes for Implementation of Advanced Methods", dated June 4, 1998. [L32 980608 800]
8. GE Letter EB-ER-98019, "Implementation ofRPTOOS and TBPOOS Analyses for Cycle 8 Browns Ferry Nuclear Plant Unit 3", dated July 6, 1998.

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 3, Page 12 Figure I APLHGR Limits for Bundle Type GE11-P9BUB323-5G5.0/4G4.0 (GE11) 15 14 13.

12

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PERATION CCEPTABLE 0 UNA 10

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4-8.

E cL' o.

6 5.

ABLE OP ERAT ACCEPT ION 0

0.0 10.0 20.0 30.0 Cyclo Exposuro (GWD/ST) 40.0 50.0 Average Planar LHGR

Exposure, Limit, GWD/ST kw/ft Most Ulniting Lattice for Each Exposure Point Average Planar LHGR Exposure,, Limit, GWD/ST kw/ft Average Planar LHGR Exposure Limit GWD/ST kw/ft 0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 10.41 10.44 10.54 10.75 11.01 11.30 11.62 11.95 7.0 8.0 9.0 10.0 12.5 15.0 17.5 20.0 12.21 12.42 12.64 12.82 12.70 12.38 12.06 11.73 25.0 30.0 35.0 40.0 45.0 50.0 55.0 57.70 10.97 10.25 9.57 8.93 8.24 7.49 6.55 6.08 Those values apply to both Turbine Bypass In4ervice and Out-OfNeNlce.

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Core Operating Limits Report TVA-COLR-BF3CS Revision 3, Page 13 Figure 2 APLHGR Limits for Bundle Type GE11-P9HUB323-8G4.0 (GE11) 15.00 14.00

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13.00 12.00

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11.00 10.00

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9.00

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6.00

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7.00 6.00 5.00

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4.00

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3.00 2.00

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UNACCEPTABLEOPERATION ACCEPTABLEOPERATION 0.00

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0 10.0 20.0 30.0 Cycle Exposuro (GWD/ST) 40.0 50.0 Average Planar LHGR Exposure 'Limit GWD/ST kw/ft Most Umiting Lattice for Each Exposure Point Average Planar

'HGR Exposure "'imit GWD/ST

'wlft Average Planar LHGR Exposure Limit GWD/ST kw/ft 0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 10.81 10.83 10.91 11.36 11.63 11.93 12.25 7.0 8.0 9.0 10.0 12.5 15.0 17.5 20.0 12.38 12.51 12.65 12.79 12.71 12.39 12.07 11.72 25.0 30.0 35.0 40.0 45.0 50.0 55.0 57.72 10.97 10.25 9.57 8.93 8.25 7.51 6.58 6.10 These values apply to both Turbine Bypass ln-Service and Out-Of4orvice.

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3CS Revision 3, Page 14 Figure 3 APLHGR Limits for Bundle Type GE11-P9HUB325-14GZ (GE11) 15.00 14.00 13.00

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12.00.

UNACCEPTABLE 0PERATION 11.00 10.00

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9.00

~

8.00 E

7.00 o.

6.00 5.00 4.00 ACCEPTABLE OPERATION 0.00 0.0 10.0 20.0 30.0 Cycto Exposure (GWD/ST) 40.0 50.0 Average Planar

...LHGR Exposure

... Limit

.. GWD/ST, kw/ft Most Umiting Lattice for Each Exposure Point

. Average Planar LHGR

. Average Planar LHGR i Exposure i

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Limit Exposure Limit GWD/ST,, kw/ft GWD/ST kw/ft 0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 9.48 9.57 9.79 10.08 10.38 10.71 11.06 11.44 7.0 8.0 9.0 10.0 12.5 15.0 17.5 20.0 11.80 12.07 12.23 12.37 12.36 12.13 11.90 11.59 25.0 30.0 35.0 40.0 45.0 50.0 55.0 57.27 10.87 10.18 9.52 8.88 8.24 7.60 6.81 6.41 These valuos apply to both Turbine Bypass ln-Service and Out-Of4ervice.

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3CS Revision 3, Page 15 Figure 4 APLHGR Limits for Bundle Type PSDRB2S3 (LTA)

(P8X8R) 15.0 14.0 13.0 12.0

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11.0 10.0 UNACCEPTABLEOPERATION 9.0 ACCEPTABLE OPERATION E

6.0 7.0 o.

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 Cyclo Exposuro IGWD/STI Average Planar LHGR Exposure

'L'imit GWD/ST

'w/ft

'verage Planar LHGR Exposure'

" 'imit GWD/ST kw/ft.

Average Planar LHGR Exposure Limit GWD/ST kw/ft 0.2 1.0 5.0 10.0 11.2 11.2 11.7 12.0 15.0 20.0 25.0 30.0 12.0 11.9 11.3 10.8 35.0 40.0 45.0 10.4 10.0 9.5 Those vaiuos apply to both Turbine Bypass In-Sorvice and Out-Of-Service.

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 3, Page 16 Figure 5 APLHGR Limits for Bundle Type P8DRB314 (LTA)

(P8X8R) 15.0 14.0 13.0

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12.0 11.0 10.0 9.0 E

8.0 7.0 o.

6.0 5.0 4.0 3.0 2.0 1.0 0.0

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ACCEPTABLEOP UNACCEPTABLEOPERATION ERATIO 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 Cyclo Exposure (GWD/ST)

Average Planar LHGR

'xposure

'imit GWD/ST kw/ft Average Planar LHGR

'Exposure Limit GWD/ST kw/ft Average Planar,,LHGR Exposure Limit GWD/ST kw/ft 0.2 1.0 5.0 10.0 10.6 10.7 11.3 11.7 15.0 20.0 25.0 30.0 11.5 11.2 10.6 10.1 35.0 40.0 45.0 9.7 9.3 8.8 These values apply to both Turbine Bypass In-Service and Out-of4orvlco.

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3CS Revision 3, Page 17 Figure 6 APLHGR Limits for Bundle Type PSDRB299 (P8X8R) 15.00 14.00

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13.00 12.00 11.00 ~

10.00 9.M

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UNACCEPTABLEOPERATION 6.00 E

7.00 ACCEPTABLE OPE RATION 6.00 5.00 4.00 3.00 1.00 O.M 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 cyclo Exposure (Gwo/ST)

Average Planar LHGR

'xposure Limit GWD/ST kw/ft Average Planar LHGR Exposure Limit GWD/ST '"' 'w/ft Average Planar LHGR Exposure Limit GWD/ST

'w/ft 0.0 0.2 1.0 2.0 3.0 4.0 10.71 10.75 10.86 11.01 11.19 11.35 5.0 6.0 7.0 8.0 9.0 10.0 11.47 11.62 11.78 11.95 12.09 12.20 12.5 15.0 20.0 25.0 35.0 42.13 12.37 12.47 12.37 11.77 10.65 9.36 These values apply to both Turbine Bypass In-Service and Out-Of4ervice.

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3C8 Revision 3, Page 18 Figure 7 APLHGR Limits for Bundle Type BP8DRB284L (GE7B or BP8X8R) 15.0

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14.0 13.0 12.0

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11.0

~

10.0

~

9.0.

E 8.0

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3 7.0

~

6.0.

5.0 4.0 3.0

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2.0 1.0 UNACCEPTABLE OPERATION ACCEPTABLEOPERATION 0.0 0

5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 Cyclo Exposure (GWD/STl

'verage'Planar

'L'HGR Exposure'imit GWD/ST kw/ft

'verage Planar 'HGR Exposure Limit GWD/ST 'w/ft Average Planar LHGR ExposureLimit GWD/ST kw/ft 0.2 1.0 5.0 10.0 11.2 11.3 11.8 12.0 15.0 20.0 25.0 30.0 12.0 11.9 11.3 10.8 35.0 40.0 45.0 10.1 9.4 8.8 These values apply to both Turbine Bypass In4ervice and Out-OfService.

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3CS Revision 3, Page 19 Figure S APLHGR Limits for Bundle Type PSDRB284Z (P8X8R) 15.0 14.0 13.0 12.0 11.0 10.0

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9.0.

UNACCEPTABLEOPERATION 6.0 E

7.0

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6.0 ERATION TABLEOP ACCEP 5.0 4.0 3.0 2.0 1.0 0.0

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

, Average Planar

LHGR, Average Planar LHGR Exposure Limit

'xposure Limit GWD/ST kw/ft GWD/ST kw/ft Average Planar, LHGR Exposure Limit GWD/ST kw/ft 0.2 1.0 5.0 10.0 11.2 11.2 11.7 12.0 15.0 20.0 25.0 30.0 12.0 11.9 11.3 10.8 35.0 40.0 45.0 10.4 9.9 9.5 These values apply to both Turbine Bypass ln-Sorvlco and Out-Of4ervlce.

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3CS Revision 3, Page 20 Figure 9 APLHGR Limits for Bundle Type PSDRB265L (P8X8R) 15.0 14.0

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13.0

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12.0

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11.0 UNACCEPTABLEOPERATION 10.0-9.0 8.0 E

7.0.

g.

6.0 5.0.

ACCEPTAB TION LE OPERA 4.0 3,0

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2.0

~

1.0 0.0

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

Average Planar LHGR Exposure Limit GWD/ST 'w/ft Average Planar LHGR

, Exposure, Limit GWD/ST kwlft

, Average Planar LHGR Exposure Limit,,

GWD/ST kw/ft 0.2 1.0 5.0 10.0 11.6 11.6 12.1 12.1 15.0 20.0 25.0 30.0 12.1 11.9 11.3 10.7 35.0 40.0 10.2 9.6 These values apply to both Turbine Bypass In4ervice and Out-Of-Service.

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3CS Revision 3, Page 21 Figure 10 MCPR Oyeratmg Limitfor PSXSR 4 GE7B (BPSXSR) 1.41 1.40 1.39 1.38 O

1.37 '

1.36 E

ra 1.35.

B 1.34 O

1.33 1.32 1.31

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RPTOOS TBOOS 1.30 1.29 0

01 Option B Turblno Bypass and Roclrculatlon Pump Trip InNorvtco I

I 0.2 0,3 0.4 0.5 0.6 0.7 0.8 0.9 1

Option A Tau (q)

'Exposure Range BOC8 to EOC8 BOC8 to EOCS Out-Ofhce rvice na Turbine B ass BOOS Option A Tau=1.0 1.33 1

1.38

,Option B Tau=0.0 1.30 BOGS to EOCS Recirculation Pum Tri RPTOOS 1.40 1.32 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.

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

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3CS Revision 3, Page 22 Figure 11 MCPR Operating Limitfor GE11 1,46 1.45 1.44 1.43 O

1.42 1.41 1.4

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1.39

~

E c

1.38

~

Ol 137 1.36 o 135.

1.34 1.33 TOOS RP TBOOS 1.32 1.31 Turbine Bypass and Recirculation Pump Trip In<ervice I

I I

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 (z)

Exposure Range BOC8 to EOC8 BOC8 to EOC8 BOC8 to EOC8 Out-Of<ervice na Turbine B ass BOOS Recirculation Pum Tri RPTOOS Option A Tau=1.0 1.35 1

1.40 1.45 Option B Tau=0.0.

1.32 1.37 1.37 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.

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

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF3CS Revision 3, Page 23 (Final)

Figure 12 GEXL-Plus KfCurve 1.40 OLMCPR Flow Corrections 1.25 ~-

None 117.I%i 112.011 107.0'h 102.5'/e 1.20 ~-

1.15 1.10 1.05

~

0,95

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20 30 40 50 60 70 80 100 110 Total Coro Flow (% ratod)

For 40% < WT

< 100%,

WT 40 WT

> 100%,

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

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

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 Modo

'ANUAL MANUAL MANUAL MANUAL AUTOMATIC Scoop Tube Sotpoint 102.5%

107 0 112.0%

117 0%o na 1.3308 1.3528 1.3793 1.4035 1.4410 Note:

Flow Corrections are given for PSX8R and BP8XSR 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% core flow.

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