ML18038B266
| ML18038B266 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/24/1995 |
| From: | Keys A, Welch K TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18038B265 | List: |
| References | |
| NUDOCS 9505030334 | |
| Download: ML18038B266 (24) | |
Text
TVA-CPLR-BF2CS Revision 1, Psge 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:
~
S <&
Kenneth
. Welch, Engineering'Specialist BWR Fuel Engineering Verified By:
A an L. Bruce, Nuclear Engineer BWR Fuel Engineering Date:
3 l> 'I4 Approved By:
T. A. Keys, anager BWR Fuel Engineering Reviewed By:
Date: 5 Zt Reactor Engineering Sup is r Reviewed By:
PO C Chairman Date:
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TVANuclear F Core Operating Limits Report TVA-COLR-BF2CS Revision 1, Page 2 Revision Log
~Revi i n Date 0
10/6/94 Desecri tion Initial Release Affec ed P Change APRM flow biased rod block setpoint; incorporate changes due to Tech Spec Amendment no. 232.
5,6
TVANuclear Ft Core Operating Limits Report TVA-COLR-BF2C8 Revision 1, 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 PSxSR 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. The APLHGR limits for the GE9B bundles (GESXSNB) are for the most limiting lattice at each exposure point. The specific values for each lattice are given in Reference 6.
TVANuclear F Core Operating Limits Report TVA-COLR-BF2C8 Revision 1, Page 4
- 3. LHGR LIMIT(TECHNICALSPECIFICATION 3.5J)
The LHGR limitfor unit 2 cycle 8 is fuel type dependent, as shown below:
~FI~T~
PSX8R/BPSXSR/QUAD+
GE8X8NB LH R Limi 13.4 kw/ft 14.4 kw/ft a.
OLMCPR (TECHNICALSPECIFICATION 3.5.K/4.5.K) whichever is greater ZA ZB 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; Zow ZB Z =00 or Z
Zi = 0.90 sec (Specification 3.3.C.1 scram time limitto 20%
insertion from fullywithdrawn )
i Zi = 0.710 + 1.65 (0.053)
N 2
n ng Zi 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 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),
TVANuclear F Core Operating limits Report TVA-COLR-BF2C8 Revision 1
Page 5
- c. For the performance of Surveillance Requirement 4.5.K.2.b,
'6 shall be determined in accordance with 4.a above.
- 5. APRM FLOW BIASED ROD BLOCKTRIP SETTING (TECHNICAL SPECIFICATION 2.1.A.1.c, TABLE3.2.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 fiow 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 fiow rate in percent of rated RBM upscale flow-biased setpoint clipped at 109 percent rated reactor power.
TVANuclear F Core Operating Limits Report TVA-COLR-BF2CS Revision 1
Page 6
- 7. REFEMPlCKS
- 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.
- 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.
TVANuclear Core Operating L>mits Report TVA-COLR-BF2CS Revision 1, Page 7 Tab1l:
1 APLHGR Limits for Bundle Type GE9B-P8DWB319-9GZ (GE8X8NB)
Most LimitingLattice 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
'.81 5.91
TVANuclear Core Operating Limits Report TVA-COLR-BF2CS Revision 1, Page 8 Table 2 APLHGR Limits'forBundle Type GE9B-P8DWB325-10GZ (GE8X8NB)
Most LimitingLattice for Each Exposure Point Average PIanar Exposure
++AT}
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
~kwf-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 F Core Operating Limits Report TVA-COLR-BF2CS Revision 1, Page 9 Table 3 APLHGR Limits for Bundle Type GE9B-P8DWB326-7GZ (GE8X8NB)
Most LimitingLattice for Each Exposure Point 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 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 '
0
TVANuclear Fu Core Operating L ts Report TVA-COLR-BF2CS Revision 1, Page 10 Table 4 APLHGR Limits for Bundle Type BP8DRB301L (BP8X8R)
Average Planar Exposure K~SR 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 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 Fu Core Operating L Report TVA-COLR-BF2C8 Revision 1, Page ll Table 5
'PLHGR Limits for Bundle Type BP8DRB299 (BP8X8R)
Average Planar Exposure gQWD~
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
~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
'0.65 9.36
TVANuclear F Core Operating L>mits Report TVA-COLR-BF2C8 Revision 1, Page 12 Table 6 APLHGR Limits for Bundle Type P8DRB284L and Westinghouse QUAD+ LTAs (PSX8R)
Average Planar Exposure
{Q~&5K 0.2 1.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 APLHGR Limit
~f 11.2 11.3 11.8 12.0 12.0 11.8 11.2 10.8 10.2 9.5 8.8
TVANuclear Fu Core Operating LiMnts Report TVA-COLR-BF2CS Revision 1, Page 13 Table 7 APLHGR Limits for Bundle Type P8DRB265H (P8X8R)
Average Planar Exposure t'(~WD $T}
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
TVANuclear Fu~
Core Operating Liats Report TVA-COLR-BF2CB Revision 1, Page 14 Figure 1
MCPR Operating Limitfor PBXBR/BPBXBR/QUAD+
1.33 1.32 1.31 1.30
'E 1.29 g -1.28 1.27 1.26 1.25 1.24 1.23 (EOCS-3080) to EOCS BOCS to (EOCS-3080) 0.0 0.1 OE2 OE3 0.4 0.5 OE6 0.7 0.8 OE9 1.0 Option B Option A E~ERR BOC8 to (EOC8-3080 MWD/ST)
(EOC8-3080 MWD/ST) to EOC8 tion A Tau=i 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.
TVANuclear Fu Core Operating Liats Report TVA-COLR-BF2CS Revision 1, Page 1S E
Figure 2 MCPR Operating Limitfor GESXSNB It 1.33 1.32 1.31 1.3 g
1.29 g
128 1.27 1.26 BO CS-30&0) toE OCS-3 CS to(E OCS 0&0) 1.25 1.24 1.23 0
0.'1 OE2 OE3 OA OE5 OE6 0.7 OE8 0.9 1
Option B Option A
~E BOC8 to (EOC8-3080 MWD/ST)
(EOC8-3080 MWD/ST)to EOC8 0 tion A Tau=1.0 1.27
- 1.32 0 tion8 Tau=0.0 1.25 1.29
- Use this value at BOC8 prior to performing scram time testing.
TVANuclear Fu~
Core Operating L~ Report TVAWOLR-BF2C8 Revision 1, Page 16 (Final) 1.4 Figure 3 GEXL-Plus Kf Curve OLMCPR Flow Corrections 1.3 None 117.0,%
n2.0%
107.0%
102.5 %
1.020 30 40 60 60 70 80 80 100 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.
Fl w n
I Mod MANUAL MANUAL MANUAL MANUAL AUTOMATIC co Tu t oin 102.5 %
107.0 %
112.0 %
117.0 %
N/A 1.3308 1.3528 1.3793 1.4035 1A410
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