ML18039A767
| ML18039A767 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/08/1999 |
| From: | Bruce A, Keys T, Riley E TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18039A766 | List: |
| References | |
| TVA-COLR-BF2C11, NUDOCS 9905050018 | |
| Download: ML18039A767 (44) | |
Text
TVA,Nuclear Fuel Core Operating Litnits Rd/Ft t
TVA-COLR-BF2C11 Revision 0, Page 1
Browns Ferry Nuclear Plant Unit 2, Cycle 11 CORE OPERATING LIMITSREPORT (COLR)
TENNESSEE VALLEYAUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By:
Earl E. Riley, Eng neering Specialist BWR Fuel Engineering Date:
Verified By:
Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering Date' 3 l I
1 Approved By:
T'. A. Keys, Man ger BWR Fuel Engineering Reviewed By:
actor Engineering Supervisor nate:
Reviewed By:
PORC Chai an Date:
Revision 0 (3/31/1999) 99050500%8 990427 j PDR ADQCK 05000260 P
PORE Initial Release Pages Affected:
All
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TVANuclear Fuel Core Operating Limits'Re~t i
TVA-COLR-BF2C11 Rev'ision 0,, Page 2 Revision Log Revision Date
~Descri tion Affected Pa es 0
3/31/1999 Initial Release for New Cycle All
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TVANuclear Fuel Core Operating LimitsRe~
TVA-COLR-BF2C11 Revision 0, Page 3
- 1. INTRODUCTION This Core Operating Limits Report for Browns Ferry Unit 2, Cycle 11 is prepared in accordance with the requirements of Browns Ferry Technical. Specification 5.6.5.
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 11 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 Specifications 3.2.1 and 3.7.5)
- b. Linear Heat Generation Rate (LHGR) L'imit (Technical Specification 3.2.3)
- c. Minimum Critical Power Ratio Operating Limit(OLMCPR)
(Technical Specifications 3.2.2, 3.3.4.1, and 3'.7.5)-
- d. Average Power Range Monitor (APRM) Flow Biased Rod'Block Trip Setting (Technical Requirements Manual Section 5.3.1 and Table 3.3.4-1) e.
Rod Block Monitor (RBM) Trip Setpoints and Operability (Technical Specification Table 3.3.2.1-1) f.
Shutdown Margin (SDM) Limit (Technical Specification 3.1.1)
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TVANuclear Fuel Core Operating Limits Re~t TVA-COLR-BF2CI I Revision 0, Page 4
- 2. APLHGR LIMIT(TECHNICALSPECIFICATIONS:3.2.1 AND3.7.5)
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'he APLHGR limits for fullpower and'flow conditions for each type of fuel as.a function of exposure are shown in Figures 1-7. 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 8. Similarly, adjustments for reduced flow operation are performed using the.MAPFAC(F).corrections given in Figure 9. Both factors are multipliers.,used'to reduce the standard APLHGR limit. The most limiting power-adjusted or flow-adjusted value is taken as the APLHGR operating limitfor the off-.rated condition.
The APLHGR.limits in figures 1-7 are applicable for both Turbine Bypass In-Service and Out-Of-Service. The off-rated power and flow corrections in figures 8 and 9 bound both Turbine Bypass In-Service and Out-Of-Service operation. No corrections are required to the APLHGR limits for TBOOS for either rated or off-rated operation.
For Single Recirculation Loop Operation (SLO), the most limiting of either the SLO multiplier-or-the off-rated'MAPFAC correction is used to reduce the exposure dependent APLHGR limit. The SLO multiplier to be:applied.to this cycle is 0.84 (reference 3). It is not necessary to apply, both the off-rated.MAPFAC and'LO multiplier corrections at the same time.
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TVANuclear Fuel Core Operating LimitsRe~
t TVA-COLR-BF2C11 Revision 0, Page 5
- 3. LHGR LIMIT(TECHNICALSPECIFICATION 3.2.3)
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The LHGR limitis fuel type dependent. For unit 2 cycle 11 these limits are the same for all fuel types in the core, as shown below:
FuelType
.L'HGR:Limit GE9B (GE8X8NB) 14.4 kw/ft GE11 14.4 kw/ft GE13 14.4 kw/ft
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TVANuclear Fuel Core Operating Limits R~rt TVA-COLR-BF2Cl 1 Revision 0, Page 6
- 4. OLMCPR (TECHNICALSPECIFICATIONS 3.2.2, 3.3.4.1, AND3.7.5) a.
The MCPR Operating Limitfor rated power and flow conditions, OLMCPR(100),
is equal to the fuel type and exposure dependent limitshown in Figure 10. For cycle 11, only GE13 results are supplied since they bound all bundle types. As noted in Figure 10, an adder of 0.02 is applied for single loop operation.
The actual OLMCPR(100) value is dependent upon the scram time testing results, as described below (ref. 10):
'C = 0.0 or Cove CB whichever is greater where; 'C= 1.096.sec (analytical Option A scram time limit-based on dropout time for notch position 36) n ovc i
N 2
p +
1 65
- cz
- n where; p =
0.830 sec (mean scram time used in transient analysis-based on dropout time for notch position 36) o =
0.019 sec (standard deviation of p)
N =
Total number of active rods measured in Technical Specification Surveillance Requirement SR3.1.4.1 n = Number of surveillance rod tests performed to date in cycle v, =
Scram time~(dropout time) from fullywithdrawn to notch position 36 for the i~ rod
- b. Option A OLMCPR'limits ('C =1.0) shall be used prior to the determination of 'C in accordance with SR.3'.1.4.1.
- c. For off-rated power and flow conditions, power-adjusted and flow-adjusted operating limits are determined from Figures 1'1 and 12, respectively. The most limitingpower-dependent or flow-dependent value is taken as the OLMCPR for the off-rated condition.
- d. OLMCPR limits and off-rated corrections are. provided for Recirculation Pump Trip out-of-service (RPTOOS) or Turbine Bypass out-of-service (TBOOS) conditions (ref. 5). These events are analyzed-separately and the core is not analyzed for both, systems Out-Of-Service at the same time.
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TVANuclear Fuel Core Operating Limits Re~rt TVA-COLR-BF2CI I Revision 0, Page 7 5.'PRM FLOW BIASED ROD BLOCK'TRIP SETTING (TECHNICAL REQUIREMENTS MANUALSECTION 5.3.1 AND TABLE3.3'.4-1)
'The APRM Rod Block trip setting shall be:
SRB 5 (0.66(W-b,W) + 61%)
SRB < (0.66(W-BW) + 59%)
A'llowable Value Nominal Trip Setpoint (NTSP) where:
W=
Rod,Block setting in percent of rated thermal'power (3458 MWt)
Loop recirculation flow'rate in percent of rated Difference between two-loop and single-loop effective recirculation flow at-the same core flow (bW=0.0 for'two-loop operation)
The.APRM Rod Block trip setting is clamped at a maximum allowable value of 115%
(corresponding to-a NTSP of 113%).
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TVANuclear Fuel Core-Operating Limits Re~rt I
T VA-COLR-BF2C11 Revision 0, Page 8
- 6. ROD BLOCKMONITOR (RBM) TRIP SETPOINTS AND OPERABILITY (TECHNICALSPECIFICATION TABLE3.3.2.1-1)
The RBM trip setpoints and applicable power ranges shall be. as follows (refs. 7-9):
RBM Trip'Setpoint:
Allowable Value (AV)
Nominal Trip,Setpoint (NTSP)
LPSP IPSP HPSP LTSP - unfiltered
- filtered 27%
62%
82%
118.7%
117.7%
25%
60%
80%
1 17.0%
116.0%
(1) (2)
ITSP - unfiltered
- filtered HTSP - unfiltered
- filtered DTSP 113.7%
112.9%
108.7%
107.9%
90%
112.0%
111.2%
107.0%
106.2%
92%
(1) (2)
(1) (>)
Notes:
(1)
These setpoints are based upon a MCPR operating limitof 1.29 using a safety limitof 1.10. This is consistent with a MCPR operating limitof 1.25 using a safety limitof 1.07, as reported in references 6, 7, and 8. These setpoints bound the cycle specific Option B MCPR operating limitof 1.30.
(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).
The RBM setpoints in Technical Specification Table 3.3.2.1-1 are applicable when:
. THERMA'L'POWER
(% Rated)
Applicable ':Notes from MCPR "'
Table:3;3.2';1'-1:
) 27% and < 90%
) 90%
< 1.75
< 1.78
< 1.44 (a)
(b) (f) (h)
(a)
(b) (f) (h)
(g) dual loop operation single loop operation dual loop operation
~'otes:
(1)
The given MCPR operating limits are adjusted to correspond to a MCPR safety limitof 1.10 for dual loop operation (1.12 for single loop operation)
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The values shown correspond to operating limits of 1.70 and 1.40 given the original 1.07 MCPR safety limitused in reference 6.
(2)
Greater than 90% rated power is not attainable in single loop operation.
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TVANuclear Fuel Core Operating Limits R~rt I
TVA-COLR-BF2C11 Revision 0; Page 9
- 7. SHUTDOWN.MARGIN(SDM)'LIMIT (TCCHNICALSPECIFICATION 3.1; 1)
The core shall be subcritical with the following margin with the strongest OPERABLE control rod fullywithdrawn and all other OPERABLE control rods fully inserted.
SDM ) 0.38% dk/k
II.
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TVANuclear Fuel Core Operating Limits Re~rt TVA-COLR-BF2C11 Revision 0,, Page 10
- 8.
REFERENCES:
- 1. NEDE-24011-P-A-13, "General'Electric Standard Application for Reactor Fuel",'ugust 1996.
- 2. NEDE-.24011-P-A-13-US, "General Electric'Standard Application for Reactor Fuel (Supplement for United States)", August 1996.
- 3. Jl:-1-03447SRLR Rev. 1, "Supplemental. Reload Licensing Report for'Browns Ferry Nuclear Plant Unit 2 Reload 10 Cycle 11", March 1999.
4..J11-03447MAPL Rev. 1, "Lattice-Dependent MAPLHGRReport for Browns Ferry Nuclear Plant Unit 2 Reload'10 Cycle 1-1", March 1999.
- 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 L'ine 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 E, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL(NUMAC)- Power-Uprate Condition] for Tennessee Valley AuthorityBrowns Ferry Nuclear Plant", dated. October. 1997.
8..'EDE-28-0990.Rev.,2 Supplement E, "PRNM (APRM, RBM, and RFM) Setpoint Calculations [ARTS/MELLL(NUMAC)- Power-Uprate Condition],for Tennessee Valley AuthorityBrowns Ferry Nuclear Plant", dated October 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 JAB-T8019a, "Technical'Specification Changes for Implementation of Advanced Methods",,dated June 4, 1998.,[L32 980608 800]
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TVANuclear Fuel Core Operating Limits Re~rt TVA-COLR-BF2C11 Revision 0, Page 11 Figure 1 APLHGR Limits for Bundle Type GE13-P9DTB406-13GZ (GE13) 15 14 13.
12 UNACCEPTABLE OPERATION 10.
9.
8.
E 7.
C9 6;
ACCEPTABLE OPERATION 0
0.0
.10.0 20.0 30.0 Cycto Exposuro (GWO/ST1 40.0 50.0 Most Umiting Lattice for Each Exposure Point
- "Average'Plana'ri,
- ,
LHGR.", (j, Average;Planar,
-;;,.L'HGR
'-'-,Exposure
':L'lmlt;;
iExposure
. ',".L'imlt-GWD/ST
'w/ft i
GWD/ST': kw/ft:
,'"Average'Planar, L'HGR
'Exposure L'Imlt GWD/ST kw/ft 0.0 0.2 1.0 2.0 3.0 4;0 5.0 6.0 10.66 10.69 10.76 10.89 11.06 11.24 11.45 11.61 7.0 8.0 9.0 10.0 12.5 15.0 17.5 20.0 11.75 11.87 11.99 12.12 12.16 12.14 12.03 11.78 25.0 30.0 35.0 40.0 45.0 50.0 55.0 59.01 11.22 10.58 9.85 9.13 8.44 7.77 7.07 6.50 These values apply to both Turbine Bypass In4ervlco and Out-Of4ervlce.
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The APLHGR limits shown are for dual recirculation loop operation. For single loop operation, these values should be multiplied by the most limitingof either 0.84 or the MAPFAC correction, as described ln Section 2.
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TVANuclear Fuel Core Operating Limits~rt I
TVA-COLR-BF2C11 Revision 0, Page 12 Figure 2 APLHGR Limits for Bundle Type GE13-P9DTB401-14GZ (GE13) 15.00 14.00 13.00
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12.00
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11.00 UNACCEPTABLE OPERATIO 10.00; 9.00 8.00 E
,7.00
'.00 5.00 ACCEPTA TION BLE OPERA 4.00 3.00 2.00 1.00-0.00
'0 10.0 20.0 30.0 Cycto Exposuro (GWD/ST) 40.0 50.0 I'Average Planar "LHGR
,Exposure..
- Limit, GWD/ST kw/ft
.'Most Umiting Lattice for Each Exposure Point
'"."Average',Planar.
L'HGR"
', Average Planar L'HGR
'Exposure::,;L'imit;
'xposure Limit
'WD/ST; t kw/ft.'WD/ST kw/ft 0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 10.49 10.52 10.59 10.74 10.90 11.02 11.15 11;29 7.0 8.0 9.0 10.0 12.5 15.0 17.5 20.0 11.44 11.59 11.72 11.85 11.84 11.84 11.83 11;71 25.0 30.0
- 35.0 40.0 45.0 50.0 55.0 58.59 11;10 10.36 9.67 9.03 8.33 7.59 6.84 6.31 These values apply to both Turbine Bypass InService and Out&fService The APL'HGR limits shown are for dual recirculation loop operation. For single loop operation, these values should be multiplied by the most limitingof either 0.84 or the NtAPFAC correction, as described ln Section 2.
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TVANuclear Fuel Core Operating Limits Re~rt t
TVA-COLR-BF2C1 1 Revision 0, Page 13 Figure 3 APLHGR Limits for Bundle Type GE13-P9HTB3S4-12G4.0 (GE13) 15 14 13 12 UNACCEPTABLE OP ERATION 10 9
8.
E 7
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to ACCEPTABLE OPERATIO N 2
0 0
10.0 20.0 30.0 Cyclo Exposuro (GWD/ST) 40.0 50.0 Most Umiting Lattice for Each Exposure Point
! Average,'Planar...'LHGR'::
AverageiPlanar;LHGR Exposu're
"'.L'irnit';,
'Exposure'
' 'L'imit GWD/ST
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'w/ft:;:GWD/ST:;i kw/ft;
., Average:Planar LHGR
'Exposure Limit
. GWD/ST,: kw/ft 0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 10.09 10.15 10.31 10.52 10.75 10.99 11;25 11.48 7.0 8.0 9.0 10.0 12.5 15.0 17.5 20.0 11.71 11.95 12.16 12.28 12.16 11.88 11.56 11.24 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 These values apply to both Turbine Bypass In4ervlce and Out-Of4ervice.
Tho APLHGR limits shown are for dual recirculation loop operation. For single loop operation, these values should be multiplied by the most limitingof either 0.84 or the MAPFAC correction, as described In Section 2.
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TVANuclear Fuel Core Operating Limits Refit I
TVA-COLR-BF2C11 Revision 0, Page 14 Figure 4 APLHGR Limits for Bundle Type GE11-P9HUB366-12G4.0 (GE1'1) 15 14 13 12 UNACCEPTABLE OP ERATION 10-9 8
7 ACCEPTABLE OPERATION 0
0 10.0 20.0 30.0 Cyclo Exposure (GWD/ST) 40.0 50.0 Average, Planar
'L'HGR, xposure>>.
>>LIimi
'WD/ST
',, kw/ft Most Umlting Lattice for Each Exposure Point
- ,Average
- Planar,,
'L'HGR iExposur'e
'," ', li!., ILimit,';I GWD/ST'.: kw/ft Average Planar, L'HGR Exposure Limit
! GWD/ST
'w/ft 0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 9.55 9.62 9.80 10.05 10.32 10.58 10.84 11.11 7.0 8.0 9.0 10.0 12.5 15.0 17.5 20.0 11.39 11.67 11.81 11.95 11.92 11.72 11.48 11.20 25.0 30.0 35.0 40.0 45.0 50.0 55.0 56.17 10.51 9.84 9.19 8.55 7.91 7.26 6.59 6.42 These values apply to both Turbine Bypass InServlce and OutfServlce.
The APLHGR limits shown are for dual recirculation loop operation. For single loop operation, these values should be multiplied by the most limitingof either 0.84 or the MAPFAC correction, as described ln Section 2.
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TVANuclear Fuel Core Operating LimitsRe~t I
TVA-COLR-BF2C11 Revision 0, Page 15 Figure 5 APLHGR Limits for Bundle Type GE11-P9HUB367-14GZ (GE11) 15 14 ERATION UNACCEPTABLE OP 10 9
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7-to ACCEPTABLE OPERATIO 0
0.0 10.0 20.0 30.0 Cyclo Exposuro (GWDIST) 40.0 50.0 Most Limiting Lattice for Each Exposure Point i,"Average';Planar-.,
lLHGR::,-,, ',; jAverage',Planar,.
'.L'HGR'i; i '.'Average'Planar L'HGR';
'Exposure- '.Limit.'
'Exposure
'L'imit Exposure L'imlt
,i',: GWD/ST l,...,
.; kw/ft;,,', i,-,
GWD/ST::,,
', i. kw/ft ',i,'i '
GWD/STi~, kw/ft i
0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 9.18 9.27 9.45 9.72 10.00 10.30 10.62 10.95 7.0 8.0 9.0 10.0 12.5 15.0 17.5 20.0 11.31 11.67 11.81 11.95 11.92 11.72 11.48 11.20 25.0 30.0 35.0 40.0 45.0 50.0 55.0 56.17 10.51 9.84 9.19 8.55 7.91 7.26 6.59 6.42 These values apply to both Turbine Bypass lnService and Out-OfServlce.
The APLHGR limits shown are for dual recirculation loop operation. For single loop operation, these values should be multiplied by the most limitingof either 0.84 or the MAPFAC correction, as described In Section 2.
TVANuclear Fuel Core Operating Limits Re~t t
TVA-COLR-BF2C1 1 Revision 0, Page 16 Figure 6 APLHGR Limits for Bundle Type GE9B-PSDWB319-9GZ (GE8X8NB) 15 13 12 ~
UNACCEPTABLEOPERATION 6
9.
8.
E 7
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CsK 8
5.
ACCEPTABLE OPERATION 0
0.0 10.0 20.0 30.0 Cycle Exposure (GWDIST) 40.0 50.0
', Av'erage'Planar
'LHGR
- Exposure Limit
- ,, ".'WD/ST;'... 'w/ft Most Umiting Lattice for Each Exposure Point
'Average'.Planar.
LHGR Exposure L'imit
, GWD/ST I '.".i
. kw/ft I, I
'verage Planar:LHGR Exposure:
Limit
,'GWD/STI '
kw/ft 0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 11.64 11.68 11.77 11.88 12.01 12.12 12.22 12.32 7.0 8.0 9.0 10.0 12.5 15.0 20.0 25.0 12.49 12.65 12.77 12.86 12.86 12.62 12.06 11.47 35.0 45.0 51.2 10.41 8.81 5.91 These values apply to both Turbine Bypass In4ervlce and Out-Of4ervice.
The APLHGR limits shown are for dual recirculation loop operation. For single loop operation, these values should be multiplied by the most limitingof either 0.84 or the MAPFAC correction, as described In Section 2.
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TVANuclear Fuel Core Operating Limits Re~t t
TVA-COLR-BF2C11 Revision 0, Page 17 Figure 7 APLHGR Limits for Bundle Type GE9B-PSDWB325-10GZ (GE8X8NB) 15 14.
13.
12.
UNACCEPTABLEOPERATION 10.
9 8.
E 7
ro 5
ACCEPTABLE OPERATION 0
0 10.0 20.0 30.0 Cycle Exposure (GWD/ST) 40.0 50.0
,'Average Planar.;
'LHGR t,
. Exposure
iL'imit
. GWD/STl i',','Ii 'w/ft'!,',
'ost Limiting Lattice for Each Exposure Point
- Average'Planar'
'L'HGR'xposureiL'imit I i.'WD/ST, i
. "r', w/ft
'. l
." AverageIPlanar L'HGR
'xposure L'imit
,'WD/STiw/fti 0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 10.97 11.00 11.31 11.54 11.79 11.97 12.10 7.0 8.0 9.0 10.0 12.5 15.0 20.0 25.0 12.23 12.35 12.46 12.58 12.58 12.35 11.86 11.33 35.0 45.0 50.27 10.12 8.60 5.92 These values apply to both Turbine Bypass inService and Out-OfServlce.
The APLHGR limits shown are for dual recirculation loop operation. For single loop operation, these values should be multiplied by the most limitingof either 0.84 or the MAPFAC correction, as described in Section 2.
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TVANuclear Fuel Core Operating Limits RPPft t
TVA-COLR-BF2Cl l Revision 0, Page 18 Figure 8 Power Dependent MAPLHGRFactor - MAPFAC(P) 1.2 0.8
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re Flow
< 50% Co O,< 06.
0.4 0.2
> 50% Coro I
Flow I
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10 20 30 40 50 60 Power (% Rated):
70 80 90 100 MAPLHGR(P) = MAPFAC(P) x MAPLHGRstd MAPLHGRstd = Standard MAPLHGR Limits For 30% < P Fol'5%,>,P: NO THERMAL'IMITSMONITORING REQUIRED For 25% <'P< 30%: MAPFAC(P) =0.60+0.005(P-30%)
Fol' 50% CORE FLOW
- MAPFAC(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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TVANuclear Fuel Core Operating'Limits R8/Ft t
TVA-COLR-BF2C11 Revision 0, Page 19 Figure 9 Flow Dependent MAPLHGRFactor - MAPFAC(F)
MAXFLOW~ 102.5'/i 0.9 0.8 O
0.7
< 102/i MAXFLOW 0.6 0.5.
0.4 30 40 50 60 70 Core Flow (% Rated) 80 90 MAPLHGR(F) = MAPFAC(F) x MAPLHGRstd MAPLHGRstd = Standard MAPLHGRLimits MAPFAC(F) = IVIINIMUM(1.0,Af*Wc/100+ Bf)
Wc = % Rated Core Flow Afand Bfare Constants Given Below:
Maximum:,',:Core Flow I
,,%iRated
'02.5 107.0 Af 0.6784 0.6758
.Bf.'.4861 0.4574 These. values bound both Turbine Bypass ln-Service and Out-Of-Service.
The 102.5% maximum flowline is used for operation up to 100% rated flow.
The 107% maximum flowline is used for operation up to 105% rated flow(ICF).
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TVANuclear Fuel Core Operating LimitsR~t TVA-COLR-BF2C11 Revision 0, Page 20 Figure 10 MCPR Operating Limitfor AllBundle Types 1.43
.1.42 1:41 3
1.4.
1.39 O
1.38
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1.37 E
1.38
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g 1.35.
p9 1.34 1 33 o 132.
1.31-1.3 1.29 0
Option B 0.1 RPTOOS
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s TBOOS Turblno Bypass and Roclrculatlon Pump Trip In<orvlco 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1
Option A Tau (q)
Exposure Range; Out-Of-Service.
Option A:
Option B eau=1;0,, 'au=0;0 BOC11 to EOC11 BOC11 to EOC11 na Turbine B ass TBOOS 1.33 1
1.37 1.30 1.34 BOC11 to EOC11 Recirculation Pum Tri RPTOOS 1.42 1.34 Notes 1'. Use this value prior to performing scram time testing per SR 3.1.4.1.
- 2. Either Turbine Bypass or Recirculation Pump Trip may be Out-Of-Service.
The core is not analyzed for both TBOOS and RPTOOS at the same time.
- 3. The values shown are for dual recirculation loop operation. Increase any value shown by 0.02 for single loop operation.
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TVANuclear Fuel Core Operating Limits R t
TVA-COLR-BF2C1 1 Revision 0, Page 21 r>
Figure 11 Power Dependent MCPR(P) Limits 3.2 3
2.8
~
ee 2.6
'o 4
El/
gA IL 24-
<<e 0 O
~v 22 Y IL e>Z 2
II CL 1.8 O 0 rL A 16.
1.4 Ir 1.2
>50Ie FLOW (Eqdnmen( tn.een(ee a RpToos)
<<50% FLOW (Eqdpmen( In.sen(ee a RpToos) 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)
OPERATING LIMITMCPR P = K
- OLMCPR 100)
For P <25%
- NO THERMALLIMITSMONITORING REQUIRED'or 25% < P < Pbypass:
(Pbypass = 30%)
Kp = [Kbyp + 0.02(30%-P)]/OLMCPR(100)
Turbine B ass and RPT In<ervlce or RPT Out-Of-Service RPTOOS Kbyp = 1.97 For < 50% CORE FLOW Kbyp = 2.21 For ) 50% CORE FLOW Turbine B ass Out-Of4ervlce TBOOS Kbyp = 2.01 Kbyp = 3.01 For < 50% COREFLOW For > 50% CORE FLOW For 30% < P<45%
For 45% < P<60%
For 60% <. P
- Kp = 1.28+ 0.01340(45%-P)
- Kp = 1.15+ 0.00867(60%-P)
- Kp = 1.00+ 0.00375(100%-P)
Note:
Either Turbine Bypass or Recirculation Pump Trip may be Out-Of-Service.
The core is not analyzed for both TBOOS and RPTOOS at the same time.
0 4'l
TVANuclear Fuel Core Operating LimitsR~t TVA-COLR-BF2C1 1 vision 0, Page 22(Final)
Figure 12 Flow Dependent MCPR Operating Limit-MCPR(F) 1.7 1.6 1.5 O
1.4 MAXFLOW~ 107%
1.3 MAXFLOW < 102.0'A 1.2 30 40 50 60 70 Core Flow (% Rated)'0 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,.,
', Core'Flow l",Af
'(% Rated).
102.5 107.0
%.587
%.603 1.701 1.745 These values bound both Turbine Bypass In4ervice and Out-Of4ervlce.
These values bound both Recirculation Pump Trip In4ervice and Out-Of4ervlce Either Turbine Bypass or Recirculation Pump Trip may be Out-Of<ervice.
The core Is not analyzed for a combination of TBOOS and RPTOOS.
The 102.5% maximum flowline ls used for operation up'to 100% rated flow.
The 107% maximum flowline Is used for operation up to 105% rated flow(ICF).
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