ML18038B396
| ML18038B396 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/27/1995 |
| From: | Bruce A, Keys T, Welch K TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18038B394 | List: |
| References | |
| TVA-COLR-BF2C8, TVA-COLR-BF2C8-R02, TVA-COLR-BF2C8-R2, NUDOCS 9508280353 | |
| Download: ML18038B396 (32) | |
Text
TVANuclear Fue Core Operating Linnts Report TVA-COLR-BF2C8 Revision 2, 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:
Date:
7 I'l 95 Kenneth L. Welch, Engineering Specialist BWR Fuel Engineering Verified By:
Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering Date:
7 2,I 9K Approved By:
T. A. Keys, M ager BWR Fuel Engineering Reviewed By:
Reactor Engineering isor Date:
Z5 Reviewed By:
ORC Chairman Date:
950828035K 950727 PDR ADOCK 05000260 P
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TVANuclear Fuel Core Operating Limits Report TVAKOLR-BF2CS Revision 2, Page 2 Revision Log R~eviai e
Date 0
10/6/94
~DpiLi nn Initial Release Affect Pa All 3/24/95 Change APRM flow biased rod block setpoint; incorporate changes due to Tech Spec Amendment no. 232.
5,6 7/27/95 Revision to correct OLMCPR to agree with GE re-analysis of FWCF using corrected value for vessel level instrumentation loop response time.
6, 14, 15
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TVANuclear Fue Core Operating Limits Report TVAKOLR-BF2C8 Revision 2, 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'nd 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 3.5.1)
- 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.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 3.5.1)
The APLHGR limit for each type of fuel as a function of exposure is shown in Tables 1-7.'he 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 Fue Core Operating Limits Report TVAKOLR-BF2CS Revision 2, Page 4
,3. LHGR LIMIT(TECHNICALSPECIFICATION 3.5J)
The LHGR limitfor unit 2 cycle 8 is fuel type dependent, as shown below:
~Fu ~1T ~
LH R Li P8X8R/BPSXSR/QUAD+
GESX8NB 13.4 kw/ft 14.4 kw/ft 4.,OLMCPR (TECHNICALSPECIFICATION 3.5.K/4.5.K) whichever is greater 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; Zaw ZB Z =0.0'r Z
ZA ZB Zi = 0.90 sec (Specification 3.3.C.1 scram time limitto 20%
insertion from fullywithdrawn )
i ZB = 0.710 + 1.65 (0.053)
N 2
n ng 'ti Save 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 fod 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),
7' 1.0
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TVANuclear Fuel Core Operating Limits Report TVAKOLR-BF2C8 Revision 2, Page 5
- c. For the performance of Surveillance Requirement 4.5.K.2.b,
'C shall be determined in accordance with 4.a above.
S. APRM FLOW BIASED ROD BLOCKTRIP SETTING (TECBNICAL.
SPECIFICATION 2.1.A.l.c, TABLE3.2.C, AND SPECIFICATION 3.5.L)
The APRM Rod Block trip setting shall be:
SRB 6 (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:
5 (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.
TVANuclear Fue Core Operating Limits Report TVAKOLR-BF2CS Revision 2, Page 6
'7. REFF~NCES
- 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. 1, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 2 Reload 7 Cycle 8," July 1995.
- 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 Corporation.
6..24A5153AA, Rev. 0, "Lattice-Dependent MAPLHGR Report for Browns Ferry Nuclear Plant Unit 2 Reload 7 Cycle 8", September 1994.
- 7. Safety Evaluation by the office of Nuclear Reactor Regulation Supporting Amendment No. 232 to Facility Operating License No. DPR-52, Tennessee Valley Authority, Browns Ferry Nuclear Power Plant, Unit 2, Docket No. 50-260.
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TVANuclear Fue Core Operating Limits Report TVA-COLR-BF2C8 Revision 2, Page 7 Table 1
APLHGR Limits for Bundle Type GE9B-P8DWB319-9GZ (GE8XSNB)
Most Limiting Lattice for Each Exposure Point Average Planar'Exposure
{QW~D/ T}
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 APLHGR 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
TVANuclear Fue Core Operating Linuts Report TVAKOLR-BF2C8 Revision 2, Page 8 Table 2 APLHGR Limits for Bundle Type GE9B-PSDWB325-10GZ (GE8X8NB)
Most LimitingLattice for Each. Exposure Point Average Planar Exposure
{QWD~/
0.0 0.2 1.0 2.0 3.0 40 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 f 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
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TVANuclear Fue Core Operating Limits Report TVA-COLR-BF2C8 Revision 2, Page 9 Table 3 APLHGR Limits for Bundle Type GE9B-P8DWB326-7GZ (GE8XSNB)
Most Limiting Lattice for Each Exposure Point Average Planar Exposure Q(~WD~
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 50.5 51.4 APLHGR Limit
~f 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
II lb
TVANuclear Fu Core Operating Limits Report TVA-COLR-BF2C8 Revision 2', Page 10 Table 4 APLHGR Limits for Bundle Type BPSDRB301L (BP8XSR)
Average Planar Exposure gxWD/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 APLHGR Limit
~kw/f 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
TVANuclear Fue Core Operating Limits Report TVAKOLR-BF2C8 Revision 2, Page 11 Table 5 APLHGR Limits for Bundle Type BPSDRB299 (BP8X8R)
Average Planar Exposure
$QW~D~
0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 12.5 15.0 20.0 25.0 35.0 42.1 APLHGR Limit
~kw f 10.71 10.75 10.86 11.01
- 11. 19 11.35 11.47 11.62 11.78 11.95 12.09 12.20 12.37 12.47 12.37 11.77 10.65 9.36
TVANuclear Fu Core Operating Limits Report TVAKOLR-BF2C8 Revision 2, Page 12 Table 6 APLHGR Limits for Bundle Type PSDRB284L and Westinghouse QUAD+ LTAs (PSXSR)
Average Planar Exposure
{QW~D/'jQ 0.2 1.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 APLHGR'imit
~kw f 11.2 11.3 11.8 12.0 12.0 11.8 11.2 10.8 10.2 9.5 8.8
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TVANuclear Fu Core Operating Limits Report TVA-COLR-BF2Cg Revision 2 Page 13 Table 7 APLHGR Limits for Bundle Type P8DRB265H (PSX8R)
Average Planar Exposure
{QW~D$'IQ 0.2 1.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 APLHGR Limit
~kw/f 11.5 11.6 11.9 12.1 12.1 11.9 11.3 10.7 10.2 9.6
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TVANuclear Fu Core Operating Limits Report TVA-COLR-BF2C8 Revision 2, Page 15 Figure 2 MCPR Operating Limitfor GE8X8NB 1.31 (E~) to EOC8 1,29 gg 1.28 V
1.27 BOC8 to tEOC830BO) 1.26 1.25 1.24 0.0 0.1 0~8 0.2 0.3 0.4 0.5'.6 0.7 0.8 0.9 1.0 OgttanA Ex osure Ran e
BOC8 to (EOC8-3080 MWD/ST)
(EOC8-3080 MWD/ST) to EOC8 0 tion A Tau=1.0 1.28
- 1.32 0 tion B Tnu=0.0 1.26 1.30
- '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 2, Page 16 (Final) 1.4 Figure 3 GEXL-Plus Kf Curve OLMCPR Flow Corrections Narc 1.3 I I7.0%
I 12.0%
I07.0%
I02.5 %
1.020 30 40 50 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.
MANUAL MANUAL MANUAL MANUAL AUTOMATIC 102.5 %
107.0 %
112;0 %
117.0 %
N/A 1.3308 1.3528 1.3793 1.4035 1.4410
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