ML18039A417
| ML18039A417 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/28/1998 |
| From: | Bruce A, Keys T, Riley E TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18039A416 | List: |
| References | |
| TVA-COLR-BF2C10, TVA-COLR-BF2C10-R01, TVA-COLR-BF2C10-R1, NUDOCS 9807080143 | |
| Download: ML18039A417 (39) | |
Text
ENCLOSURE 1
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 2 CORE OPERAT ING LIMITS REPORT (COLR) I REVIS ION 1 FOR CYCLE 10 OPERATION (SEE ATTACHED) 9807080i4$ 980630 PDR ADQCK 05000260 P
PDR eY
TlANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 1
Browns Ferry Nuclear Plant Unit 2, Cycle 10 CORE OPERATING LIMITSREPORT (COLR)
TENNESSEE VALLEYAUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By:
Earl E. Riley, En eering Specialist BWR Fuel Engineering Date: <-~1-8 Verified By:
Alan L, Bruce, Nuclear Engineer BWR Fuel Engineering Date:
Approved By:
T. A. Keys, ager BWR Fuel Engineering Reviewed By:
actor Engineering Supervisor Reviewed By:
P RC Chairman Revision 1 (5/21/98)
Revise Coefficients for Tau Calculation Pages Affected:
1, 2, 6, 9
0
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 2 Revision Log Revision Date 0
9/25/97
~Descri tion Initial Release Affected Pa es All 5/21/98 Revise Tau Calculation (ref. BFN PER no. 98-005651-000)
I, 2, 6, 9
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 3
- 1. INTRODUCTION This Core Operating Limits Report for Browns Ferry Unit 2, Cycle 10 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 10 are documented in Reference 3.
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.
Average Power Range Monitor (APRM) Flow Biased Rod Block Trip Setting (Technical Specification 2.1.A.1.c and Table 3.2.C) e.
Rod Block Monitor (RBM) Trip Setpoints (Technical Specification Table 3.2.C)
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 4
- 2. APLHGR LIMIT(TECHNICALSPECIFICATION 3.5.I)
The APLHGR limits for full power and flow conditions for each type of fuel as a function of exposure are shown in Figures 1-8. The APLHGR limits for the GE9B, GE11 and GE13 assemblies are for the most limiting lattice (excluding natural uranium) at each exposure point. The specific values for each lattice are given in Reference 4.
These APLHGR limits are adjusted for off-rated power and flow conditions using the ARTS factors, MAPFAC(P) and MAPFAC(F). The reduced power factor, MAPFAC(P),
is given in Figure 9. Similarly, adjustments for reduced flow operation are performed using the MAPFAC(F) corrections given in Figure 10. Both factors are multipliers used to reduce the standard APLHGR limit. The most limiting power-adjusted or fiow-adjusted value is taken as the APLHGR operating limitfor the off-rated condition.
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Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 5
- 3. LHGR LIMIT(TECHNICALSPECIFICATION 3.5.J)
The LHGR limitfor unit 2 cycle 10 is fuel type dependent, as shown below:
Fuel Type LHGR:Limit GE7B (BP8X8R) 13.4 kw/ft GE9B (GE8X8NB) 14.4 kw/ft GE11 14.4 kw/ft GE13 14.4 kw/ft
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 6
- 4. OLMCPR (TECHNICALSPECIFICATION 3.5.K/4.5.K) a.
The MCPR Operating Limitfor rated power and fiow conditions, OLMCPR(100),
is equal to the fuel type and exposure dependent limitshown in Figures 11, 12, 13, and 14. The actual OLMCPR(100) value is dependent upon the scram time testing results, as described below:
2 =00 or Save ZB whichever is greater.
Z~ = 0.90 sec (Specification 3.3.C.1 scram time limitto 20%
insertion from fullywithdrawn )
I Zs = 0.694 + 1.65 (0.016)
N 2
n ng ri Save i=1 n
Reference 10 where; n = Number ofsurveillance rod tests performed to date in cycle (including BOC test).
Zi = Scram time to 20% insertion from fullywithdrawn ofthe i rod.
N = Total number ofactive rods measured in Specification 4.3.C. 1 at BOC.
- b. For theperformanceof Surveillance Requirement 4.5.K.2.a (prior to initial scram time measurements for the cycle),
'C = 1.0 c.
For the performance of Surveillance Requirement 4.5.K.2.b,
'C shall be determined in accordance with 4.a above.
d.
For off-rated power and flow conditions, power-adjusted and flow-adjusted operating limits are determined from Figures 15 and 16, respectively. The most limitingpower-dependent or flow-dependent value is taken as the OLMCPR for the off-rated condition.
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Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 7
- 5. APRM FLOW BIASED ROD BLOCKTRIP SETTING (TECHNICAL SPECIFICATION 2.1.A.l.c ANDTABLE3.2.C)
The APRM Rod Block trip setting shall be:
SRB < (0.66W+ 66%)
SRB < (0.66W + 64%)
Allowable Value Nominal Trip Setpoint (NTSP) where:
SRB = Rod Block setting in percent of rated thermal power (3293 MWt)
W = Loop recirculation flow rate in percent of rated The APRM Rod Block trip setting is clamped at a maximum allowable value of 115%
(corresponding to a NTSP of 113%).
0 0
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 8
- 6. ROD BLOCKMONITOR (RBM) TRIP SETPOINTS (TECHNICALSPECIFICATION TABLE3.2.C)
The RBM trip setpoints and applicable power ranges shall be as follows:
RBM~Trip Setpoint-Allowable:Value (AV)'
Nominal Trip Setpoint
'(NTSP)
LPSP 27%
25%
IPSP 62%
60%
HPSP 82%
80%
LTSP - unfiltered
- filtered 121.7%
120.7%
120.0%
119.0%
(l) (2)
ITSP - unfiltered
- filtered 116.7%
115.7%
115.0%
114.0%
(l) (2)
HTSP - unfiltered
- filtered 111.7%
110.9%
110.0%
109.2%
(>) (2)
DTSP 90%
92%
Notes:
(1)
These setpoints are based upon a MCPR operating limitof 1.34 using a safety limitof 1.10. This is consistent with a MCPR operating limitof 1.30 using a safety limitof 1.07, as reported in references 6, 7, and 8.
(2)
The unfiltered setpoints are consistent with a nominal RBM filter setting of 0.0 seconds (reference 8). The filtered setpoints are consistent with a nominal RBM filter setting ( 0.5 seconds (reference 7).
Ci TVANuclear Fuel
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Core Operating Limits Report TVA-COLR-BF2CI0 Revision 1, Page 9
- 7. 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. J11-03144SRLR Rev. 1, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 2 Reload 9 Cycle 10", September 1997.
- 4. Jl 1-03144MAPL Rev. 0, "Lattice-Dependent MAPLHGRReport for Browns Ferry Nuclear Plant Unit 2 Reload 9 Cycle 10", August 1997.
- 5. NEDC-32774P Rev. 1, "Safety Analyses for Browns Ferry Nuclear Plant Units 1, 2, and 3 Turbine Bypass and End-of-Cycle Recirculation Pump Trip Out-Of-Service", dated September 1997.
- 6. NEDC-32433P, "Maximum Extended Load Line Limitand ARTS Improvement Program Analyses for Browns Ferry Nuclear Plant Unit 1, 2, and 3", dated April 1995.
7.. EDE-28-0990 Rev. 3 Supplement F, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL(NUMAC)- Current Rated Condition] for Tennessee Valley AuthorityBrowns Ferry Nuclear Plant", dated Sept. 1997,
- 8. EDE-28-0990 Rev. 2 Supplement F, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL(NUMAC)- Current Rated Condition] for Tennessee Valley AuthorityBrowns Ferry Nuclear Plant", dated Sept. 1997.
- 9. GE Letter LBP: 262-97-133, "Browns Ferry Nuclear Plant Rod Block Monitor Setpoint Clarification - GE Proprietary Information", dated September 12, 1997.
[L32 970912 800]
10.GE letter JSC-005-086 to US NRC, "Revised Supplementary Information Regarding Amendment 11 to GE Licensing Topical Report NEDE-24011-P-A", dated January 16, 1986.
T VANuclear Fuel
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Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 10 Figure 1 APLHGR Limits for Bundle Type GE13-P9HTB384-12G4.0 (GE13) 15.
14.
13 12.
UNACCEPTABLE OPERATION 10 g
g 8
E3 rc 7-to 5
ACCEPTABLE OPERATION 0
~
0 10.0 20.0 30.0 40.0 50.0 Cycto Exposure (GWD/ST1 Average Planar Exposure GWD/ST
- LHGR Limit kw/ft Most Limiting 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 10.09 2.0 3.0 4.0 5.0 6.0 10.52 10.75 10.99 11.25 11.48 0.2 10.15 1.0
'0.31 10.0 12.5 15.0 12.16 11.88 17.5 20.0 11.56 11.24 7.0 11.71 r
8.0 11.95 9.0 12.16 12.28 25.0 30.0 35.0 40.0 45.0 50.0 55.0 55.98 10.6 9.99 9.39 8.76 8.11 7.44 6.74 6.60
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C1 0 Revision I, Page 11 Figure 2 APLHGR Limits for Bundle Type GE11-P9HUB366-12G4.0 (GE11) 15 UNACCEPTABLE OP ERATION 10
~P 8
E 7
UX ACCEPTABLE OPERATION 0
0.0 10.0 20.0 30.0 Cyclo Exposure (GWD/ST) 40.0 50.0 Average'Planar."
"'~ 'L'HGR;-.
>>Exposure'imit
=",
GWD/ST '. 'w/ft Most Limiting Lattice for Each Exposure Point
='Average Planar,
- 'LHGR:.: Average Planar
-. LHGR
=
-.Exposure:
- ""Limit':'"Exp'osure'imit GWD/ST
. kw/ft GWD/ST kw/ft 0.0 I
9.55 0.2
'.62 1.0 9.80 2.0 10.05 3.0, 10.32 7.0
~
11.39 8.0 l
11.67 9.0 11.81 12.5 11.92 10.0 11.95 30.0 9.84 35.0 9.19 40.0 8.55 45.0 7.91 25.0 10.51 4.0
)
10.58 150 11.72 50.0 7.26 5.0 6.0 10.84 11.11 17.5 11.48 20.0 11.20 55.0 6.59 56.17 6.42
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 12 Figure 3 APLHGR Limits for Bundle Type GE11-P9HUB367-14GZ (GE11) 15 14 13
~
12.
UNACCEPTABLE OPERATION 10
~
8 E
7 Ux 5
ACCEPTABLE OPERATION 0
0.0 10.0 20.0 30.0 Cycle Exposure (GWD/ST) 40.0 50.0 Most Limiting Lattice for Each Exposure Point Average'Planar,:;,.; " LHGR~."Average Planar
':: -, LHGR..".
- Exposure,'-:=
";- Limit',-".;.:="'Exposure'
'=Limit GWD/ST '
- kw/ft
'~". '
GWD/ST
~ kw/ft Average, Planar~
. Exposure Limit
'WD/ST, kw/ft 0.0 I
9.18 7.0
'1.31 25.0 10.51 0.2 I
9.27 10 I
945 80 1167 9.0 11.81 30.0 9.84 35.0 9.19 2.0 3
9.72 30 I
1000 40 i
1030 10.0
~
11.95 12.5 i
11.92 15.0:,
11.72 40.0 45.0 50.0 8.55 7.91 7.26 6.0 10.95 5.0
'0.62 11.48 17.5 20.0 11.20 6.59 55.0 56.17 6.42
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2CI0 Revision 1, Page 13 Figure 4 APLHGR Limits for Bundle Type GE9B-P8DWB319-9GZ (GE8X8NB) 15 14 13 12 UNACCEPTABLE OPERATION 8
E 7.
U 5
ACCEPTABLE OPERATION 0
0.0 10.0 20.0 30.0 Cycle Exposure (GWD/ST) 40.0 50.0 Most LimitingLattice for Each Exposure Point Average Planar L'HGR'; 'Average Planar, LHGR Exposure Limit
. 'xposure, Limit GWD/ST, kw/ft, GWD/ST
, kw/ft
- Ayera'ge Planar LHGR
. Exposure Limit GWD/ST kwlft 00 s
1164 0 2 I
11.68 1.0
'1.77 2 0 I
1188 3.0 12.01 4.0 12.12 5.0 12.22 6.0 12.32 7.0 12.49 8.0 I
12.65 90
'277 10.0 12.86 12.5
~
12.86 15.0 12.62 11.47 25.0 20.0 12.06 35.0 45.0 51.2 10.41 8.81 5.91
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Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 14 Figure 5 APLHGR Limits for Bundle Type GE9B-PSDWB325-10GZ (GE8X8NB) 15 13.
12
~
BLE OPERATIO UNACCEPTA g
8 E
7 to 8
ACCEPTABLE OPERATION 0
0 10.0 20.0 30.0 Cycle Exposure (GWD/ST) 40.0 50.0 Average Planar.. LHGR Exposure.",, Limit GWD/ST '.. ', kw/ft Most Limiting Lattice for Each Exposure Point Average Planar LHGR
-, Exposure.,
Limit GWD/ST 'wlft Average Planar LHGR
-Exposure Limit GWD'/ST kwlft 0.0
'0.97 0.2 I
11.00 1 0 I;
11 11 7.0
~i 12.23 80
'235 9.0 12.46 35.0 45.0 50.27 10.12 8.60 5.92 2.0 11.31 3.0 I
11.54 10.0 12.5 12.58 12:58 4.0 11.79 15.0 12.35 II 11.97 5.0 6.0 12.10 20.0 25.0 11.86 11.33
TVANuclear Fuel
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Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 15 Figure 6 APLHGR Limits for Bundle Type GE9B-PSDWB326-7GZ (GE8X8NB) 15 UNACCEPTABLE OPERATION C!
8.
E 7
Ux ACCEPTABLE OPERATION 0
0.0 10.0 20.0 30.0 Cyclo Exposure (GWD/ST) 40.0 50.0 Average Planar 'LHGR
.'xposure"
~
Limit
'WD/ST, kwlft Most LimitingLattice for Each Exposure Point
'Average",Planar.'HGR
'verage Planar LHGR
'Exposure
- Limit, Exposure Limit
. GWD/ST kw/ft GWD/ST kw/ft 0.0 I
11.45 0.2 i
11.47 7.0 i
12.31 8.0 I
12.41 35.0 10.15 45.0 8.72 3.0
'1.87 4.0 I
12.01 50
'213 6.0 12.22 1.0 I
11 55 2.0
"'1.70 15.0 12.41 20.0
'1.91 25.0 11.35 9.0
'2.51 100 I
1263 12.5 12.64 50.49 5.93
'I TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 16 Figure 7 APLHGR Limits for Bundle Type BPSDRB301L (BP8X8R) 15 14 13.
12 UNACCEPTABLEOPERATION 10
~
8 E
IL 7
t9 ACCEPTABLE OP ERATION 2
~
0 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 cyclo Exposure (GWD/ST)
Average Pla'nar
'LHGR iAv'erage Planar'.. "."LHGR" "
Exp'osure
.Limit 'xpo'sure'imit GWD/ST,.
kw/ff.';.,
'WD/ST
'w/ft "Average Planar LHGR Expo'sure Limit GWD/ST kwlft 0.0 11.32 0.2 11.33 1.0 2.0 11.40 11.50 3.0 i
11.61 6.0 11.93 4 0
'173 5 0 l
1186 7.0 I
11.98 8.0 I
12.03 9.0
.'12.11 100
'219 12.5, 12.34 25.0 12.03 15.0
~
12.47 20.0 12.58 350
'082 43.52 9.17
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 17 Figure S APLHGR Limits for Bundle Type BPSDRB299 (BP8X8R) 15 14 13
~
12.
UNACCEPTABLE OPERATION 10.
E 8
3 IL' (a
ACCEPTABLE OPE RATION 3
0 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0
'yclo Exposure (GWD/ST) 40.0 Average'Planar" LHGR Ex'pos'ure" Limit GWD/ST kw'Ift 0.0
'0.71 02 I
1075 1.0 10.86 2.0 11.01 3.0 11.19 Average, Planar
'HGR Exposure "
Limit GWD/ST kw/ft 7.0 I
11.78 8.0; 11.95 9.0, 12.09 10.0 12.20 12.5
'2.37 10.65 9.36 35.0 42.13 Average Planar LHGR Exposure Limit GWD/ST kwlft 5.0 11.47 11.62 6.0 4.0
'1.35 15.0 20.0 25.0 12.47 12.37 11.77
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Core Operating Limits Report TVA-COLR-BF2CI0 Revision 1, Page 18 Figure 9 Power Dependent MAPIHGR Factor - MAPFAC(P) 1.2 0.8
< 50% Core Flow g+ 0.6
~
0.4 0.2 I
I e Flow I
I I
~ 50% Cor 10 20 30 40 50 60 70 80 90 100 Power (% Rated)
MAPLHGR(P) = MAPFAC(P) x MAPLHGRstd MAPLHGRstd =, Standard MAPLHGR Limits For 30% (P For 25% ) P
'NOTHERMALLIMITSMONITORINGREQUIRED For 25% < P< 30%; MAPFAC(P) 0.60+0005(P 30%)
For c 50% CORE FLOW
'APFAC(P) = 0.46+ 0.005(P-30%)
Fol' 50% CORE FLOW
- MAPFAC(P) = 1.0+ 0.005224(P-100%)
These values bound both Turbine Bypass In-Service and Out-Of-Service
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Core Operating Limits Report TVA-COLR-BF2CI0 Revision l, Page 19 Figure 10 Flow Dependent MAPLHGRFactor - MAPFAC(F)
MAXFLOW ~ 102.5%
0.9.
0.8 O
0.7 MAXFLOWi 107%
0.6 0.5 0.4.
30 40 50 60 70 Coro Flow (% Rated) 80 90 100 MAPLHGR(F) = MAPFAC(F) x MAPLHGRstd MAPLHGRstd = Standard MAPLHGRLimits MAPFAC(F) = MINIMUM(1.0,Af* Wc /100+ Bf)
Wc =% Rated Core Flow Afand Bfare Constants Given Below:
Maximum, =
- Coie Flow
(% Rated)-
102.5 107.0 0.6784 0.6758 0.4861 0.4574 These values bound both Turbine Bypass In-Service and Out-Of-Service.
The 102.5% maximum flow line is used for operation up to 100% rated flow.
The 107% maximum flow line is used for operation up to 105% rated flow (ICF).
0
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Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 20 Figure 11 MCPR Operating Limitfor GE13 1.43 1.42 1.41 CPf O
o 1.39 B
1.36 4 1.37.
B O 1.36.
oc g 1.35.
Turbin Ice ut-Of4erv e Bypass 0 Turbine Bypass InNervlce 1.33 0
Option B 0.1 0.2 0.3 0.4 0.5 0.6
, 0.7 0.6 0.9 1
Option A Tau (q)
Exposure Range BOC10 to EOC10 Out-'Of-Service "
- 4 na "Option A Tau=,1.'0 1.37 1
Option'B'au=0.0 1.34 BOC10 to EOC10 Turbine B pass 1.41 1.38 Notes
- 1. Use this value at BOC10 prior to performing scram time testing.
~,
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 21 Figure 12 MCPR Operating Limitfor GE11 1.43
~
1.42 1.41-CIf 14.
O o
1.39 I
5 1.38
=
1.37 CL<
1.36 m 1.35.
Turbine Byp Nefvlce ass Out&1 Turbine Bypass In<ervice 1.33 0
Option B 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1
Option A Tau (q)
Exposure" Rang'e BOC10 to EOC10 BOC10 to EOC10
- , Out-Of;Serytce'.,-;
na Turbine B ass
, -.Option'A Tau=1.0 1.35 1
1.39 Option B
, Ta'u=0.0 1.34 1.36 Notes
- 1. Use this value at BOC10 prior to performing scram time testing.
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 22 Figure 13 MCPR Operating Limitfor GE9B (GESXSNB) 1.39
~
1.38 C)
CI 1.37 O
o 1.36.
E g 1.35.
1.34 oO 1.33 urblne Bypass Out-0f<ervlce Turb!no Bypass In<orvico 1.32 0
Option B 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1
Option A Tau (q)
,Exposure"'Range.'OC10 to EOC10 BOC10 to EOC10
'" Out-Of-Service,
'a Turbine B pass
.,'ption'A
'Tau=1.0 1.34 1
1.36
'Option B Tau=0.0 1.34 1.34 Notes
- 1. Use this value at BOC10 prior to performing scram time testing.
0
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 23 Figure 14 MCPR Operating Limitfor GE7B (BPSXSR) 1.39 1.38 CI ID 1.37 O
I 1.36 E
g 1.35.
L 1.34 O
Turbine Bypass In<ervice &Out&f<ervice 1.33 1.32 0
01 Option B 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1
Option A Tau (q)
Exposure Range BOC10 to EOC10 BOC10 to EOC10 E
Out-Of-Service na Turbine B pass Option A Tau=1.0 1.34 1
1.34 Option B Tau=0.0 1.34 1.34 Notes
- 1. Use this value at BOC10 prior to performing scram time testing.
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 1, Page 24 Figure 15 Power Dependent MCPR(P) Limits 3.2 I
>505'LOW tTBOOS)
CO Ol OS CL 0
thIh 0
IO A
0~ V CL Y L 0
0 pg CL C X CL A 0 0
'U Cl lO 2.8 2.6 2.4 2.2 1.8 1.6 1.4 1.2 5505'LOw 550% FL0WpBOOS) 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)
OPERATING LIMITMCPR P = K 'LMCPR 100 For P < 25%
~ NO THERMALLIMITSMONITORING REQUIRED For 25% < P < Pbypass For 30% < P<45%
For 45% < P<60O For 60% < P (Pbypass = 30%)
Kp = (Kbyp + 0.02(30%-P)J/OLMCPR(100)
Turbine B ass In&ervice Kbyp =1.97 For < 50% CORE FLOW Kbyp = 2.21 For >
50% CORE FLOW Turbine B ass Out-Of-Service Kbyp = 2.01 For <
50% CORE FLOW Kbyp = 3.01 For >
50% CORE FLOW Kp = 1.28+ 0.01340(45%-P)
Kp = 1.15+ 0.00867(60%-P)
Kp = 1.00+ 0.00375(1 00%-P)
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Core Operating Limits Report TVA-COLR-BF2CI0 Revision 1, Page 25 (Final)
Figure 16 Flow Dependent MCPR Operating Limit-MCPR(F) 1.7 1.6 1.4 07'A MAXFLOW ~ 1 MAXFLOW s 102.5%
1.2 30 40 50 60 70 Coro Flow I% Ratod) 80 90 100 For Wc
< 40%
For Wc ) 40
- MCPR(F) = (Af'Wc/100+ Bf)'[1+0.0032(40-Wc)]
- MCPR(F) = MAX(1.23,Af'Wc/100+ Bf)
Wc =% Rated Core Flow Afand Bfare Constants Given Below:
"."Maximum" i
. 'Coro Flow;,"'.
%'Rated)','02.5 107.0
~... I
='k.'f.",
%.587
%.603 1.701 1.745 These values bound both Turbine Bypass In-Service and Out-Of-Service The 102.5% maximum flowline is used for operation up to 100% rated flow.
The 107% maximum flow line is used for operation up to 105% rated flow(ICF).