ML18038A985
| 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: |
| 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 LIMITSREPORT (COLR)
TENNESSEE VALLEYAUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering Verified By:
Earl E. Riley, Nu lear Engineer BWR Fuel Engineering Date:
~</~~~5'pproved By:
T. A. Keys, Man ger BWR Fuel Engineering Reviewed By Reactor Engineering S or Date:
tC Reviewed By:
ORC Chairman Date:
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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C8 Revision 0, Page 2 Revisioa I,og Revision Date 0
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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C8 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(TECHNICALSPECIFICATION 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.
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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C8 Revision 0, Page 4
- 3. LHGR LIMIT(TECHNICALSPECIFICATION 3.5.J)
The LHGR limitfor unit 2 cycle 8 is fuel type dependent, as shown below:
~Fuel T e
P8X8R/BP8X8R/QUAD+
GE8X8NB LHGR Limit 13.4 kw/ft 14.4 kw/ft 4.
OLMCPR (TECHNICALSPECIFICATION 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 limitto 20%
insertion from'fullywithdrawn )
t Z~ = 0.710 + 1.65,, (0.053)
N 2
t.l."11,
~ l Ltn eng 7r Zave n
where; n = Number ofsurveillance rod tests performed to date in cycle (including BOC test).
Zi = Scram time to 20% insertion from fullywithdrawn ofthe i th 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),
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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2CS 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 BLOCKTRIP SETTING (TECHNICAL SPECIFICATION 2.1.A.I.c, TABLE3.2.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 TABLE3.2.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.
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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2CS 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 MAPLHGRReport for Browns Ferry Nuclear Plant Unit 2 Reload 7 Cycle 8", September 1994.
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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C8 Revision 0, Page 7 Table 1
APLHGR Limits for Bundle Type GE98-P8DWB319-9GZ (6E8X8NB)
Most LimitingLattice for Each Exposure Point Average Planar Exposure
~GWD/S 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 45.0 51.20 APLICGR Limit kw/ft 11.64 11.68 11.77 11.88 12.01 12.12 12.22 12.32 12.49 12.65 12.77 12.86 12.86 12.62 12.06 11.47 10.41 8.81 5.91
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TVANuclear Fuel
'Core Operating Limits Report TVA-CQLR-BF2CS 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
~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 45.0 50.27 APLHGR Limit kw/ft 10.97 11.00 11.11 11.31 11.54 11.79 11.97 12.10 12.23 12.35 12.46 12.58 12.58 12.35 11.86 11.33 10.12 8.60 5.92
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2CS Revision 0, Page 9 Table 3 APLHGR Limits for Bundle Type GE9B-P8DWB326-7GZ (GE8X8NB)
Most LimitingLattice for Each Exposure Point Average Planar Exposure
~GWD/ST 0.0 0.2 1.0 2.0 30 40 5.0 6.0 7.0.
8.0 9.0 10.0 12.5t
'5.0'0.0 25.0 35.0' 45.0 50.5 51.4 APLHGR Limit km/ft 11.45 11.47 11.55 11.70 11.87 12.01 12.13 12.22 12.31 12.41 12.51 12.63 12.64 12.41 11.91 11.35 10.15 8.72 5.93 5.87
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2CS Revision 0, Page 10 Table 4 APLHGR Limits for Bundle Type BP8DRB301L (BP8X8R)
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 43.5 fj]
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~i APLHGR Limit kw/ft 11.32 11.33 11.40 11.50 11.61 11.73 11.86 11.93 11.98 12.03 12.11 12.19 12.34 12.47 12.58 12.03 10.82 9.17
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TVANuclear Fuel Core Operating Linuts Report TVA-COLR-BF2CS Revision 0, Page 11 Table 5 APLHGR Limits for Bundle Type BP8DRB299 (BP8X8R)
Average Planar Exposure
~GWD/S 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 42.1 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
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2CS Revision 0, Page 12 Table 6 APLHGR Limits for Bundle Type P8DRB284L and Westinghouse QUAD+ LTAs (PSX8R)
Average Planar Exposure
~GWD/S 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 11.8 11.2 10.8 10.2 9.5 8.8
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2CS Revision 0, Page 13 Table 7 APLHGR Limits for Bundle Type P8DRB265H (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 11.5 11.6 11.9 12.1 12.1 11.9 11.3 10.7 10.2 9.6
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MCPR Operating Limitfor P8X8R/BP8X8R/QUAD+
1.33 1.32 1.31 1.30 1.29 1.28 1.27 1.26 1.25 (EOCS-3080) to EOCS BOC8 to (EOCS-3080) 1.24'.23 0.0 0.1 0.2 0;3
.0.4 0.5 0.6 Option B 0.7'.8 0.9 1.0 Option A F~l* "
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BOC8'o (EOC8-3080 MWD/ST)
(EOC8-3080.MWD/ST) to EOC8 0 tion A Tau=1.0 1.26
- 1.30 0 tion B Tau=0.0 1.25 1.27
": Use this value at BOC8 prior to performing scram time testing.
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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C8 Revision 0, Page 15 Figure 2 MCPR Operating Limitfor GE8X8NB 1.33 1.32 1.31 1.30 (EOC8-3080) to EOC8 1.29 1.28 g
1.27 1.26
,BOC8 ho (BOC8-3080) 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 BOC8 to (EOC8-3080 MWD/ST)
(EOC8-3080'MWD/ST). to EOC8 0 tion A Tan=1.0 1.27
"'.32
~O~iB h
=h.ll 1.25 1.29
": Use this value at BOC8 prior to performing scram time testing.
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TVANuclear Fuel Core Operating Limits eport TVA-COLR-BF2C8 Revision 0, 'Page 16 (Final)
'I.4 Fi.gure 3 GEXL-Plus Kf Curve OLMCPR Flow Corrections None 1.3 117.0 %
112.0 %
107.0 %
102.5 %
1.'0 30 40 60 60 70 80 Total Core Flow (% rated) 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 Scop Tube Set oint MANUAL MANUAL MANUAL MANUAL AUTOMATIC 102.5 %
107.0 %
112.0 %
117.0'%/A 1.3308 1.'3528 1.3793 1.4035 1.4410
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