ML18038A985

Cycle 8,Core Operating Limits Rept.

ML18038A985
Person / Time
Site:	Browns Ferry
Issue date:	10/06/1994
From:	Bruce A, Keys T, Riley E TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18038A984	List: ML18038A983 ML18038A985
References
TVA-COLR-BF2C8, TVA-COLR-BF2C8-R, TVA-COLR-BF2C8-R00, NUDOCS 9411070211
Download: ML18038A985 (32)

Text

TVA-COLR-BF2CS Revision 0, Page 1 Browns Ferry Nuclear Plant Unit 2, Cycle 8 CORE OPERATING LIMITS REPORT (COLR)

TENNESSEE VALLEYAUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering Verified By: Date:

Earl E. Riley, Nu lear Engineer BWR Fuel Engineering ~</~~~5'pproved By:

T. A. Keys, Man ger BWR Fuel Engineering Reviewed By Date: tC Reactor Engineering S or Reviewed By: Date: IO b t I ORC Chairman J

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TVA Nuclear Fuel TVA-COLR-BF2C8 Core Operating Limits Report Revision 0, Page 2 Revisioa I,og Revision Date D~escri tioo Affected Pa es 0 10/03/94 Initial Release All ii H

lk TVANuclear Fuel TVA-COLR-BF2C8 Core Operating Limits Report Revision 0, Page 3

1. INTRODUCTION This Core Operating Limits Report for Browns Ferry Unit 2, 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 2, Cycle 8 are documented in Reference 3.

The cycle 8 loading includes four Westinghouse QUAD+ demonstration assemblies.

The locations of these assemblies satisfy the criteria specified in References 4 and 5.

Evaluations performed by Westinghouse (Reference 5) show that the results of licensing analyses for the lead P8x8R fuel assembly bound those for the QUAD+

demonstration assemblies. Cycle specific analyses confirm this conclusion.

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. AP~ Plpw Biased Rod Block Trip Setting (Technical Specification 2.1.A.l.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 limit for each type of fuel as a function of exposure is shown in Tables 1-7. The APLHGR limits for the GE9B bundles (GE8X8NB) are for the most limiting lattice at each exposure point. The specific values for each lattice are given in Reference 6.

0 TVANuclear Fuel TVA-COLR-BF2C8 Core Operating Limits Report Revision 0, Page 4

3. LHGR LIMIT(TECHNICAL SPECIFICATION 3.5.J)

The LHGR limit for unit 2 cycle 8 is fuel type dependent, as shown below:

~Fuel T e LHGR Limit P8X8R/BP8X8R/QUAD+ 13.4 kw/ft GE8X8NB 14.4 kw/ft 4 . OLMCPR (TECHNICAL SPECIFICATION 3.5.E/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; Z =00 or whichever is greater.

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

insertion from'fully withdrawn )

t N 2 Z~ = 0.710 + 1.65,, (0.053) t.l."11, ~ l Ltn en g 7r Zave n

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

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

Cl II TVA Nuclear Fuel TVA-COLR-BF2CS Core Operating Limits Report Revision 0, Page 5

c. For the performance of Surveillance Requirement 4.5.K.2.b, 'C shall be determined in accordance with 4.a above.

5. APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL SPECIFICATION 2.1.A.I.c, TABLE 3.2.C, AND SPECIFICATION 3.5.L)

The APRM Rod Block trip setting shall be:

SRB < (0.58W + 50/o) 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 TABLE 3.2.C)

The RBM Upscale trip setting shall be:

s (0.66W + 43%)

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 109 percent rated reactor power.

Il 4l TVANuclear Fuel TVA-COLR-BF2CS Core Operating Limits 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. 24A5153, Rev. 0, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 2 Reload 7 Cycle 8," September 1994.

4. Safety Evaluation by the office of Nuclear Reactor Regulation Supporting Amendment No. 125 to Facility Operating License No. DPR-52, Tennessee Valley Authority, Browns Ferry Nuclear Power Plant, Unit 2, Docket No. 50-260.

5. WCAP-10507 dated March 1984, "QUAD+ Demonstration Assembly Report,"

Westinghouse Electric Corportion.

6. 24A5153AA, Rev. 0, "Lattice-Dependent MAPLHGR Report for Browns Ferry Nuclear Plant Unit 2 Reload 7 Cycle 8", September 1994.

V 'V A ~ ~ a'*' s c i ~ %v e" b e i .v > ~

TVA Nuclear Fuel TVA-COLR-BF2C8 Core Operating Limits Report Revision 0, Page 7 Table 1 APLHGR Limits for Bundle Type GE98-P8DWB319-9GZ (6E8X8NB)

Most Limiting Lattice for Each Exposure Point Average Planar Exposure APLICGR Limit

~GWD/S kw/ft 0.0 11.64 0.2 11.68 1.0 11.77 2.0 11.88 3.0 12.01 4.0 12.12 5.0 12.22 6.0 12.32 7.0 12.49 8.0 12.65 9.0 12.77 10.0 12.86 12.5 12.86 15.0 12.62 20.0 12.06 25.0 11.47 35.0 10.41 45.0 8.81 51.20 5.91

4l TVA Nuclear Fuel TVA-CQLR-BF2CS

'Core Operating Limits Report Revision 0, Page 8 Table 2 APLHGR Limits for Bundle Type GE9B-P8DWB325-10GZ (GE8X8NB)

Most Limiting Lattice for Each Exposure Point Average Planar Exposure APLHGR Limit

~GWD/ST kw/ft 0.0 10.97 0.2 11.00 1.0 11.11 2.0 11.31 3.0 11.54 4.0 11.79 5.0 11.97 6.0 12.10 7.0 12.23 8.0 12.35 9.0 12.46 10.0 12.58 12.5 12.58 15.0 12.35 20.0 11.86 25.0 11.33 35.0 10.12 45.0 8.60 50.27 5.92

TVA Nuclear Fuel TVA-COLR-BF2CS Core Operating Limits Report Revision 0, Page 9 Table 3 APLHGR Limits for Bundle Type GE9B-P8DWB326-7GZ (GE8X8NB)

Most Limiting Lattice for Each Exposure Point Average Planar Exposure APLHGR Limit

~GWD/ST km/ft 0.0 11.45 0.2 11.47 1.0 11.55 2.0 11.70 30 11.87 40 12.01 5.0 12.13 6.0 12.22 7.0. 12.31 8.0 12.41 9.0 12.51 10.0 12.63 12.5t 12.64

'5.0'0.0 12.41 11.91 25.0 11.35 35.0' 10.15 45.0 8.72 50.5 5.93 51.4 5.87

TVANuclear Fuel TVA-COLR-BF2CS Core Operating Limits Report Revision 0, Page 10 Table 4 APLHGR Limits for Bundle Type BP8DRB301L (BP8X8R)

Average Planar Exposure APLHGR Limit

~GWD/ST kw/ft 0.0 11.32 0.2 11.33 1.0 11.40 2.0 fj] 11.50 3.0 II 11.61 4.0 11.73 5.0 11.86 6.0 11.93 7.0 11.98 8.0 12.03 9.0 12.11 10.0 l. 12.19 12.5 ~i 12.34 15.0 12.47 20.0 12.58 25.0 12.03 35.0 10.82 43.5 9.17

Cl TVA Nuclear Fuel TVA-COLR-BF2CS Core Operating Linuts Report Revision 0, Page 11 Table 5 APLHGR Limits for Bundle Type BP8DRB299 (BP8X8R)

Average Planar Exposure APLHGR Limit

~GWD/S kw/ft 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 35.0 10.65 42.1 9.36

TVA Nuclear Fuel TVA-COLR-BF2CS Core Operating Limits Report Revision 0, Page 12 Table 6 APLHGR Limits for Bundle Type P8DRB284L and Westinghouse QUAD+ LTAs (PSX8R)

Average Planar Exposure APLHGR Limit

~GWD/S kw/ft 0.2 11.2 1.0 11.3 5.0 11.8 10.0 12.0 15.0 12.0 20.0 11.8 25.0 11.2 30.0 10.8 35.0 10.2 40.0 9.5 45.0 8.8

TVA Nuclear Fuel TVA-COLR-BF2CS Core Operating Limits Report Revision 0, Page 13 Table 7 APLHGR Limits for Bundle Type P8DRB265H (P8X8R)

Average Planar Exposure APLHGR Limit

~GWD/ST kw/ft 0.2 11.5 1.0 11.6 5.0 11.9 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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. w ~~~ ~ < v TVA Nuclear Fuel TVA-'COLR-BF2CS Core Operating Limits Report Revision 0, Page 14 Figure 1 MCPR Operating Limit for P8X8R/BP8X8R/QUAD+

1.33 1.32 1.31 1.30 1.29 (EOCS-3080) to EOCS 1.28 1.27 .

1.26 BOC8 to (EOCS-3080) 1.25 1.24'.23 0.0 0.1 0.2 0;3 .0.4 0.5 0.6 0.7'.8 0.9 1.0 Option B Option A F~l* " " R*" 0 tion A Tau=1.0 0 tion B Tau=0.0 BOC8'o (EOC8-3080 MWD/ST) 1.26

• 1.25 (EOC8-3080.MWD/ST) to EOC8 1.30 1.27 Use this value at BOC8 prior to performing scram time testing.

~ 'Ihh' ' 'hh ~ ~ hw hh'h I'IJA'h h, w 8>> -h ', ~ ~ h*. ~ ~ h h -" hhu ~ ~ h ~: h 'h'h hV' h TVA Nuclear Fuel TVA-COLR-BF2C8 Core Operating Limits Report Revision 0, Page 15 Figure 2 MCPR Operating Limit for GE8X8NB 1.33 1.32 1.31 (EOC8-3080) to EOC8 1.30 1.29 1.28 g 1.27

,BOC8 ho (BOC8-3080) 1.26 1.25 1.24 I 1.23 0.0 0.1 Oh2 0;3: 0'.4'h5 0.6'.7'.8 0.9 1.'0 Option B .Option A'KR 0 tion A Tan=1.0 ~O~iB h =h.ll BOC8 to (EOC8-3080 MWD/ST) 1.27

"'.32 1.25 (EOC8-3080'MWD/ST). to EOC8 1.29 Use this value at BOC8 prior to performing scram time testing.

0 TVANuclear Fuel TVA-COLR-BF2C8 Core Operating Limits eport Revision 0, 'Page 16 (Final)

Fi.gure 3 GEXL-Plus Kf Curve OLMCPR Flow Corrections

'I .4 None 117.0 %

1.3 112.0 %

107.0 %

102.5 %

1.'0 30 40 60 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' 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 Scop Tube Set oint MANUAL 102.5 % 1.3308 MANUAL 107.0 % 1.'3528 MANUAL 112.0 % 1.3793 MANUAL 117.0'%/A 1.4035 AUTOMATIC 1.4410

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