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| number = ML18038B973
| number = ML18038B973
| issue date = 09/26/1997
| issue date = 09/26/1997
| title = Cycle 10 Colr.
| title = Cycle 10 Colr
| author name = BRUCE A L, KEYS T A, RILEY E E
| author name = Bruce A, Keys T, Riley E
| author affiliation = TENNESSEE VALLEY AUTHORITY
| author affiliation = TENNESSEE VALLEY AUTHORITY
| addressee name =  
| addressee name =  
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:t TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision.0, Page 1 Browns Ferry Nuclear Plant Unit 2, Cycle 10 CORE OPERATING LIMITS REPORT (COLR)TENNESSEE VALLEY AUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By: Earl.E.Riley, Engineering Specialist BWR Fuel Engineering Da~e: Verified By Alan L.Bruce, Nuclear Engineer BWR Fuel Engineering.Approved By: T;A.'Keys, Ma ger BWR Fuel Engineering Date Reviewed By: eactor Engineering Supervisor Date: Reviewed.By: PORC Chairman Date: 97i02iOi48 9'7iOi5 PDR ADQCK 050002bO P PDR 0 i' l TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 2 Revision Log Revision Date 0 9/25/97 D~escri tion Initial Release AfFected Pa es All r-'4 1 TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 3'.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.
{{#Wiki_filter:t TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision.0, Page 1
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'.S.I)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.l.c and Table 3.2:C)e.Rod Block Monitor (RBM)Trip Setpoints (Technical, Specification Table 3.2:C) il ,~
Browns Ferry Nuclear Plant Unit 2, Cycle 10 CORE OPERATING LIMITSREPORT (COLR)
TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision'0, Page 4 ,2.APLHGR LIMIT (TECHNICAL SPECIFICATION 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).
TENNESSEE VALLEYAUTHORITY Nuclear Fuel Division BWR Fuel Engineering Department Prepared By:
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 flow-adjusted value is taken as.the APLHGR operating limit for, the ofF-rated condition.
Earl.E. Riley, Engineering Specialist BWR Fuel Engineering Da~e:
Ik ll TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page'5 3.LHGR LIMIT (TECHNICAL SPECIFICATION 3.5.J)The LHGR limit for unit 2 cycle 10 is fuel type dependent, as shown below: GE7B (BP8X8R)13.4 kw/ft GE9B (GE8X8NB)14.4 kw/ft GE11 14.4 kw/ft GE13 14;4 kw/ft 0 I' TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 6 4;OLMCPR (TECHNICAL SPECIFICATION 3.5.K/4.5.K).a.The MCPR Operating Liinit for rated power and flow conditions, OLMCPR(100), is equal to the fuel type and exposure dependent limit shown in Figures 11, 12, 13, and 14.The actual OLMCPR(100) value is dependent upon the scram time testing results, as described below:=0.0 Zme ZB of ZA ZB whichever is greater.'5=0.90 sec (Specification 3.3.C.1 scram time limit to 20%insertion from fully withdrawn)i Z~=0.710+1.65'(0.053)N~n n g zi i=i Zave n where;n=Number of surveillance rod tests'performed to date in cycle (including BOC test).Zi=Scram time to 20%insertion from fully withdrawn of.the i foil.N=Total.number of active 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),'6=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.
Verified By Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering
The most limiting power-dependent or flow-dependent value is taken as.the OLMCPR for the of-rated condition.
.Approved By:
II t TVA Nuclear Fuel Core Operating Limits Report'VA-COLR-BF2C10 Revision 0, Page 7 5.APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL SPECIFICATION 2.1.A.l.c AND TABLE 3.2.C)The APRM Rod Block, trip setting shall be: 'SRB 5 (0;66W+66Ão)
T; A.'Keys, Ma ger BWR Fuel Engineering Date Reviewed By:
SRB g (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 jo (corresponding to a NTSP of 113/o).
eactor Engineering Supervisor Date:
Ih TVA Nuclear Fuel Core Operating Limits Rcport TVA-COLR-BF2C10 Revision 0, Page 8 6.ROD BLOCK MONITOR (RBM)TRIP SETPOINTS (TECHNICAL SPECIFICATION TABLE 3.2.C)The RBM trip setpoints and applicable power ranges, shall be as follows: LPSP 27%25%IPSP 62o/60%HPSP 82%80%LTSP-unfiltered
Reviewed. By:
-filtered, 121 7%120.7%120 0%119 0%(1)(2)ITSP-unfiltered
PORC Chairman Date:
-filtered 116.7%115.7%115.0%114.0%(1)(>)HTSP-unfiltered
97i02iOi48 9'7iOi5 PDR ADQCK 050002bO P
-filtered.111.7%1.10.9%110.0%109.2%(1)(2)DTSP 90%92%Notes: (1)These setpoints are based upon a MCPR operating limit of 1.34 using a safety limit of 1.10.This is consistent with a MCPR operating limit of 1.30 using a safety limit of 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).
PDR
Ik TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, 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.Jl 1-03144SRL'R Rev.1,"Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 2 Reload 9 Cycle 10", September 1997.4.Jl 1-03:144MAPL Rev.'0,"Lattice-Dependent MAPLHGR Report 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 Limit-and 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]
0 i'
for Tennessee Valley Authority Browns Ferry Nuclear Plant", dated Sept.1997.'8.EDE-28-0990'Rev.
 
2 Supplement F,"PRNM (APRM, RBM, and RFM)Setpoint Calculations
l TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 2 Revision Log Revision Date 0
[ARTS/MELLL (NUMAC)-Current Rated Condition]
9/25/97 D~escri tion InitialRelease AfFected Pa es All
for Tennessee Valley Authority Browns Ferry Nuclear Plant", dated, Sept.1997.9.GE Letter LBAt: 262-97-133,"Browns Ferry Nuclear Plant Rod Block Monitor Setpoint Clarification
 
-GE Proprietary Information", dated September 12, 1997.,[L32 970912 800]
r- '4
4l l TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 10 15 14 13 Figure 1 APLHGR Limits for Bundle Type GE13-P9HTB384-12G4.0 (GE13)12.UNAC CEPTABLE OP E RATION 10 9 ,8 lY 7 (o o.6 ACCEPTABLE OPERATION 0 0 0 10.0 20.0 30.0 Cycle Exposure (GWDIST)40.0 50.0''AVe'rage::Plai1arp,":.:'::i,,:,''."L'HGR::;-;!:;:i);;
 
1 TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 3'.INTRODUCTION This Core Operating Limits Report for Browns: Ferry Unit 2, Cycle 10 is prepared in accordance with the requirements ofBrowns 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'.S.I)
: 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.l.c and Table 3.2:C)
: e. Rod Block Monitor (RBM) Trip Setpoints (Technical, Specification Table 3.2:C)
 
il
, ~
 
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision'0, Page 4
,2. APLHGRLIMIT(TECHNICALSPECIFICATION 3.5."I)
The APLHGR limits for fullpower 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 flow-adjusted value is taken as. the APLHGR operating limitfor, the ofF-rated condition.
 
Ik ll
 
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page'5
: 3. LHGRLIMIT(TECHNICALSPECIFICATION 3.5.J)
The LHGR limitfor unit 2 cycle 10 is fuel type dependent, as shown below:
GE7B (BP8X8R) 13.4 kw/ft GE9B (GE8X8NB) 14.4 kw/ft GE11 14.4 kw/ft GE13 14;4 kw/ft
 
0 I '
 
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 6 4; OLMCPR (TECHNICALSPECIFICATION 3.5.K/4.5.K)
.a.
The MCPR Operating Liinitfor rated power and flow 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:
= 0.0 Zme ZB of ZA ZB whichever is greater.
'5 = 0.90 sec (Specification 3.3.C. 1 scram time limitto 20%
insertion from fullywithdrawn )
i Z~ = 0.710 + 1.65 (0.053)
N
~
n ng zi i=i Zave n
where; n = Number ofsurveillance rod tests'performed to date in cycle (including BOC test).
Zi = Scram time to 20% insertion from fullywithdrawn of.the i foil.
N = Total. number of active 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),
'6 = 1.0 c.
For the performance ofSurveillance 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 of-rated condition.
 
II t
 
TVANuclear Fuel Core Operating LimitsReport'VA-COLR-BF2C10 Revision 0, 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 5 (0;66W+66&#xc3;o)
SRB g (0 66W + 64')
Allowable Value Nominal Trip Setpoint (NTSP) where:
SRB.=:Rod Block setting in percent ofrated thermal power (3293 MWt)
W = Loop recirculation flow rate in percent ofrated The APRM Rod Block trip setting is clamped at a maximum allowable value of 115 jo (corresponding to a NTSP of 113/o).
 
Ih
 
TVANuclear Fuel Core Operating Limits Rcport TVA-COLR-BF2C10 Revision 0, Page 8
: 6. ROD BLOCKMONITOR(RBM) TRIP SETPOINTS (TECHNICALSPECIFICATION TABLE3.2.C)
The RBM trip setpoints and applicable power ranges, shall be as follows:
LPSP 27%
25%
IPSP 62o/
60%
HPSP 82%
80%
LTSP - unfiltered
- filtered, 121 7%
120.7%
120 0%
119 0%
(1) (2)
ITSP - unfiltered
- filtered 116.7%
115.7%
115.0%
114.0%
(1) (>)
HTSP - unfiltered
- filtered.
111.7%
1.10.9%
110.0%
109.2%
(1) (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 of0.0 seconds (reference 8). The filtered setpoints are consistent with a nominal RBM filter setting < 0.5 seconds (reference 7).
 
Ik
 
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, 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. Jl 1-03144SRL'R Rev. 1, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 2 Reload 9 Cycle 10", September 1997.
: 4. Jl 1-03:144MAPL 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, "MaximumExtended Load Line Limit-and 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 Authority Browns 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 Authority Browns Ferry Nuclear Plant", dated, Sept. 1997.
: 9. GE Letter LBAt: 262-97-133, "Browns Ferry Nuclear Plant Rod Block Monitor Setpoint Clarification - GE Proprietary Information", dated September 12, 1997.
,[L32 970912 800]
 
4l l
 
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 10 15 14 13 Figure 1 APLHGR Limits for Bundle Type GE13-P9HTB384-12G4.0 (GE13) 12.
UNACCEPTABLE OP ERATION 10 9
,8 lY 7
(o o.
6 ACCEPTABLE OPERATION 0
0 0 10.0 20.0 30.0 Cycle Exposure (GWDIST) 40.0 50.0
''AVe'rage::Plai1arp,":.:'::i,,:,''."L'HGR::;-;!:;:i);;
",>".';;:.:",'.;.Ei'Pastire'.:::,":,::;,:'.I:;,::-;'::;:-:I.'im'i':,.':.;
",>".';;:.:",'.;.Ei'Pastire'.:::,":,::;,:'.I:;,::-;'::;:-:I.'im'i':,.':.;
Most Limiting Lattice for Each Exposure Point ,::;Ave'raqe,:P.lanai~~:.;.:::;::,'I HGR;:;"Si':,;Average'.,Planar)~::-;::L'HGR"~
Most Limiting Lattice for Each Exposure Point
0.0 0.2 1.0 2.0 3.0 4.0 10.09 10.15 10.31 10.52 10.75 10.99 7.0 8.0 9.0 10.0 12.5 15.0 11.71 11.95 12.16 12.28 12.16 11.88 25.0 30.0 35.0 40.0 45.0 50.0 10.6 9.99 9.39 8.76 8.11 7.44 5.0 6.0 11.25 11.48 17 51.1.56 20.0 11.24 55.0 55.98 6.60 0
,::; Ave'raqe,:P.lanai~~:.;.:::;::,'I HGR;:;"Si ':,;Average'.,Planar)~::-;::L'HGR"~
TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-'BF2C10 Revision 0, Page 11 Figure 2 APLHGR Limits for Bundle Type GE11-P9HUB366-12G4.0 (GE11)15 14 13 12 UNAC CEPTABLE OPERATION 10 p 9 8 E, 7 U o.6 5 I 4 ACCEPTA BLE OPERATIO N 0 0 0 10.0 20.0 30.0 Cycle Exposure (GWDIS'f)40.0 50.0;Avera'ge.:.:Pla'vari,::::::::,';.:,":,:.;".,::ILHGR(':,::.:,'
0.0 0.2 1.0 2.0 3.0 4.0 10.09 10.15 10.31 10.52 10.75 10.99 7.0 8.0 9.0 10.0 12.5 15.0 11.71 11.95 12.16 12.28 12.16 11.88 25.0 30.0 35.0 40.0 45.0 50.0 10.6 9.99 9.39 8.76 8.11 7.44 5.0 6.0 11.25 11.48 17 51.1.56 20.0 11.24 55.0 55.98 6.60
'j~-.;j.EXji0S4rP
 
~:;-"~~"'~:;;(jib,imit;;-'(;;;',':
0
::;!':::, 6WDIS.::":-;::;:::::,:.:';,',::"::::,":::.
 
kwlft:,": Most Limiting Lattice for Each Exposure Point';;,":Averige':.;Plariar",',::,:::,'-:.:::.:;,':.".:L'HGR:::;.":
TVANuclear Fuel Core Operating Limits Report TVA-COLR-'BF2C10 Revision 0, Page 11 Figure 2 APLHGR Limits for Bundle Type GE11-P9HUB366-12G4.0 (GE11) 15 14 13 12 UNACCEPTABLE OPERATION 10 p
'.'!.'""A" GWDIS'':>"."I'c."."':
9 8
i"''"'$ft!:"Average Plaiiar@k5'.:::LHGRP~
E, 7
'0.0 0.2 1.0 9.55 9.62 9.80 7.0 11.39 8.0 11.67 9.0 11.81 30.0 9.84 35.0 9.19 25.0 10.51 2.0 3.0 4.0 5.0 6.0 10.05 10.32 10.58 10.84 10.0 12.5 15.0 17.5 20.0 11'.95 11.92 11.72 11.48 11.20 40.0 45.0 50.0 55.0 56.17 8.55 7.91 7.26 6.59 6.42 41 TVA Nuclear Fuel Core Operating Limits Rcport TVA-COLR-BF2C10 Revision 0, Page 12 Figure,3 APLHGR Limits for Bundle Type GE11-P9HUB367-14GZ (GE11)15 14 13 UNACCEPTABLE OPERATION 10 9 8 7 ts'5 ACCEPTA BLE OPERATIO N ,3 0 0 0 10.0 20.0 30.0 Cyme Exposure (GWDIST)40.0 50.0:;:~A'aerage;:,PIanii.':.:,':,~F(!:-::.'ILHGR:,",.;:.j:;
U o.
;;:;:<::::::;"',,BX fiostirA";:I:;:,:::>>;.:;;-.;,:,';;;:::::
6 5
Limit;,:,::,":;.;
I 4
'.4!'=GIND'18''.,';:.:;.:-;:":"'..';
ACCEPTABLE OPERATION 0
6'ih:,-::-":.:
0 0 10.0 20.0 30.0 Cycle Exposure (GWDIS'f) 40.0 50.0
Most Limiting Lattice for Each Exposure Point;!Average::Planar~"';:'lHGR(j 0.2 9;27 1.0 9.45 9.'72 2.0 0.0 9.18 7.0'.0 9.0 10.0 11.31 11.67 11.81 11.95 25.0 30.0 35.0 40.0 10.51 9.84 9.19 8.55 3.0 4.0 5.0'.0 10.00 10.30 10.62.10.95 12.5 15.'0 17.5 20.0 1,1;92 11.72 1'1.48 11.20 45.0 50.0 55.0 56.17 7.91 7.26 6.59 6.42 ih 4l>>
;Avera'ge.:.:Pla'vari,::::::::,';.:,":,:.;".,::ILHGR(':,::.:,'
TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 13'Figure 4 APLHGR Limits for Bundle Type GE9B-PSDWB319-9GZ (GESXSNB)15 14 13 12 UNACCEP TABLE OPERATION 10 9 8 E 7 U o.'6 5 ACCEPTABLE OPERATION 4 0 0.0 10.0 20.0 30.0 Cycle Exposure (GWDIST)40.0 50.0;;;;,;",':
'j~-.;j.EXji0S4rP ~:;-"~~"'~:;;(jib,imit;;-'(;;;',':
EIt'P0SMri~:;:,:;:.".,';:;",':::,:,,",:.','.;.Limit>>:,'-.",'.-:.:
::;!':::, 6WDIS.::":-;::;:::::,:.:';,',::"::::,":::.kwlft:,":
Most Limiting Lattice for Each Exposure Point';";,'Averige':Planar-::.:::,"'."".K'Ak':HGRg:;-.'";;
Most Limiting Lattice for Each Exposure Point
:;'.-,:,'Ayera'ge::Planar Sg"':::,LHSR@m
';;,":Averige':.;Plariar",',::,:::,'-:.:::.:;,':.".:L'HGR:::;.":
'.".-':<Geois<l..':""::..':::.>>
'.'!.'""A"GWDIS
itWe;<>>::.'::.>>~
'':>"."I'c."."':i"''"'$ft
GWDIS..";k:<4k@VIft;.
!:"Average Plaiiar@k5'.:::LHGRP~
0.0 11.64 11.68 0.2 1.0 11;77 7.0 12.49 8.0 12.65 12.77 9.0 35.0 10.41 45.0 8.81 51.2 5.91 2.0 3.0 4.0 5.0 6.0 11.88 12.01 12.'12 12.'22 12.32 10.0 12.5 15.0 20.0'25.0 12.86 12.86 12.62 12.06 11.47 Ik TVA Nuclear Fuel Core Operating Limits Report'VA-COLR-BF2C10'evision 0, Page 14.15 14 13 12'BLE OPERATIO UNACCEPT Figure 5 APLHGR Limits for Bundle Type GE9B-P8DWB325-10GZ (GE8XSNB)10 9 8 E 7 (o x o.6 ACCEPTABLE OPERATION 4 0 00'0.0 20.0 30.0 Cycle Exposure (GWDISTI 40.0 50.0 Most Limiting Lattice for Each Exposure Point-AVera96::PJaltarjj,.-:,:...jLHGR.:'!.:':::'::
'0.0 0.2 1.0 9.55 9.62 9.80 7.0 11.39 8.0 11.67 9.0 11.81 30.0 9.84 35.0 9.19 25.0 10.51 2.0 3.0 4.0 5.0 6.0 10.05 10.32 10.58 10.84 10.0 12.5 15.0 17.5 20.0 11'.95 11.92 11.72 11.48 11.20 40.0 45.0 50.0 55.0 56.17 8.55 7.91 7.26 6.59 6.42
,'j'Average'::Planar"',.',>>.".":I;."-",;L'HGR~:,'Qa":Planar'~:.='.;.".:'.LHGR@
 
0.2 11.00 1.0 11.11 0.0 10.97 7.0 12.23 12.46 9.0 8.0 12.35 35.0 45.0 50.27 10.12 8.60 5.92 2.0 3;0 4.0 5.0 6.0 11.31 11.54 1-1.79 11.97 12.10 10.0 12.5 15.0 20.0 25.0 12.58 12.58 12.35 11.86 11.33 Ib TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-'BF2C10 Revision 0, Page 15 15 14 Figure 6 APLHGR Limits for Bundle Type GE9B-PSDWB326-7GZ (GE8X8NB)13 12.UNACCE PTABLE'OPE RATION 10 9 E 8 7 U'.6 5 ACCEPTABLE OPERATION 3 0.0 0 10.0 20.0 30.0 Cyde Exposure (GWD/ST)40.0::::.Av'clay'e::Planar,,;';,'g.::::.'.;::.LHGR;":.::::":;.',?
41
 
TVANuclear Fuel Core Operating LimitsRcport TVA-COLR-BF2C10 Revision 0, Page 12 Figure,3 APLHGR Limits for Bundle Type GE11-P9HUB367-14GZ (GE11) 15 14 13 UNACCEPTABLE OPERATION 10 9
8 7
ts' 5
ACCEPTABLE OPERATION
,3 0
0 0 10.0 20.0 30.0 Cyme Exposure (GWDIST) 40.0 50.0
:;:~A'aerage;:,PIanii.':.:,':,~F(!:-::.'ILHGR:,",.;:.j:;
;;:;:<::::::;"',,BXfiostirA";:I:;:,:::>>;.:;;-.;,:,';;;:::::Limit;,:,::,":;.;
'.4!'= GIND'18
''.,';:.:;.:-;:":"'..'; 6'ih:,-::-":.:
Most Limiting Lattice for Each Exposure Point
;!Average::Planar~"';:'lHGR(j 0.2 9;27 1.0 9.45 9.'72 2.0 0.0 9.18 7.0'.0 9.0 10.0 11.31 11.67 11.81 11.95 25.0 30.0 35.0 40.0 10.51 9.84 9.19 8.55 3.0 4.0 5.0'.0 10.00 10.30 10.62
.10.95 12.5 15.'0 17.5 20.0 1,1;92 11.72 1'1.48 11.20 45.0 50.0 55.0 56.17 7.91 7.26 6.59 6.42
 
ih 4l>>
 
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 13
'Figure 4 APLHGR Limits for Bundle Type GE9B-PSDWB319-9GZ (GESXSNB) 15 14 13 12 UNACCEPTABLEOPERATION 10 9
8 E
7 U
o.
'6 5
ACCEPTABLE OPERATION 4
0 0.0 10.0 20.0 30.0 Cycle Exposure (GWDIST) 40.0 50.0
;;;;,;",': EIt'P0SMri~:;:,:;:.".,';:;",':::,:,,",:.','.;.Limit>>:,'-.",'.-:.:
Most Limiting Lattice for Each Exposure Point
';";,'Averige':Planar-::.:::,"'."".K'Ak':HGRg:;-.'";;:;'.-,:,'Ayera'ge::Planar Sg"':::,LHSR@m
'.".-':< Geois
<l..':""::..':::.>> itWe;<>>::.'::.>>~ GWDIS..";k:<4k@VIft;.
0.0 11.64 11.68 0.2 1.0 11;77 7.0 12.49 8.0 12.65 12.77 9.0 35.0 10.41 45.0 8.81 51.2 5.91 2.0 3.0 4.0 5.0 6.0 11.88 12.01 12.'12 12.'22 12.32 10.0 12.5 15.0 20.0
'25.0 12.86 12.86 12.62 12.06 11.47
 
Ik
 
TVANuclear Fuel Core Operating Limits Report
'VA-COLR-BF2C10'evision 0, Page 14
.15 14 1312'BLE OPERATIO UNACCEPT Figure 5 APLHGR Limits for Bundle Type GE9B-P8DWB325-10GZ (GE8XSNB) 10 9
8 E
7 (ox o.
6 ACCEPTABLE OPERATION 4
0 00'0.0 20.0 30.0 Cycle Exposure (GWDISTI 40.0 50.0 Most Limiting Lattice for Each Exposure Point
-AVera96::PJaltarjj,.-:,:...jLHGR.:'!.:':::'::,'j'Average'::Planar"',.',>>.".":I;."-",;L'HGR~:,
'Qa":Planar'~:.='.;.".:'.LHGR@
0.2 11.00 1.0 11.11 0.0 10.97 7.0 12.23 12.46 9.0 8.0 12.35 35.0 45.0 50.27 10.12 8.60 5.92 2.0 3;0 4.0 5.0 6.0 11.31 11.54 1-1.79 11.97 12.10 10.0 12.5 15.0 20.0 25.0 12.58 12.58 12.35 11.86 11.33
 
Ib
 
TVANuclear Fuel Core Operating Limits Report TVA-COLR-'BF2C10 Revision 0, Page 15 15 14 Figure 6 APLHGR Limits for Bundle Type GE9B-PSDWB326-7GZ (GE8X8NB) 13 12.
UNACCEPTABLE'OPERATION 10 9
E 8
7 U'.
6 5
ACCEPTABLE OPERATION 3
0
.0 0 10.0 20.0 30.0 Cyde Exposure (GWD/ST) 40.0
::::. Av'clay'e::Planar,,;';,'g.::::.'.;::.LHGR;":.::::":;.',?
,:.,i',:i!!i'Ntf)IS'T,'i!i:.'":i:::.k$
,:.,i',:i!!i'Ntf)IS'T,'i!i:.'":i:::.k$
::l':,'.-'.:';
::l':,'.-'.:'; tei'ilft'i" ":
tei'ilft'i"": Most Limiting Lattice for Each Exposure Point;':,'Avera9e;PIartar'-:;::.:,'''
Most Limiting Lattice for Each Exposure Point
~.;:: LHGR:::;',':
;':,'Avera9e;PIartar'-:;::.:,'''
:;"."Averar'Ie::Pfatla'r,,:;.'.';>j'.::,LHGR;g
~.;:: LHGR:::;',': :;"."Averar'Ie::Pfatla'r,,:;.'.';>j'.::,LHGR;g
~: '','."'GWDI8T.S.".'5Nh>>ki7iilft,"..'.0 0.2 1.0 11;45 11.47 11;55 7.0 8.0 9.0 12.31 12.41 12.51 35.0 45.0 50.49 10.15 5.93 2.0 11.70 10.0 12.63 3.0 11.87 12.5 12.64 4.0 12.01 15.0 12.41 5.0 6.0 12.13 12.22 11.35 25;0 20.0 11.91 If.l TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 16 Figure 7 APLHGR Limits for Bundle Type BP8DRB301L (BP8X8R)15 14 13 12 UNACCEPTABLE OPERATION 10 8 E 7 U ABLE OP ACCEPT ERATION 0 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 Cyde Exposure (GWDIST)';,IAVersgj;Pjariar:,'";,.;"..::.',",:>,.l-,;;;:l.'HOT;,".,'.:
~:
'','."'GWDI8T. S.".'5Nh>>
ki7iilft,"..'.0 0.2 1.0 11;45 11.47 11;55 7.0 8.0 9.0 12.31 12.41 12.51 35.0 45.0 50.49 10.15 5.93 2.0 11.70 10.0 12.63 3.0 11.87 12.5 12.64 4.0 12.01 15.0 12.41 5.0 6.0 12.13 12.22 11.35 25;0 20.0 11.91
 
If
.l
 
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 16 Figure 7 APLHGR Limits for Bundle Type BP8DRB301L (BP8X8R) 15 14 13 12 UNACCEPTABLE OPERATION 10 8
E 7
U ABLEOP ACCEPT ERATION 0
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 Cyde Exposure (GWDIST)
';,IAVersgj;Pjariar:,'";,.;"..::.',",:>,.l-,;;;:l.'HOT;,".,'.:
:::::.'-':;:.'::-."'GV'io'is
:::::.'-':;:.'::-."'GV'io'is
'""M:.3'.".':::.;
'""M:.3'.".':::.;'kwi8'':J.":
'kwi 8'':J.": ':,;.'Aspera'ge,::Phriat;,,;,':'.g,.K:.'::.'::,1',HGR;:".:,-"..:.'.)K.k'0:;Eltp 0$tt fe jNK@j~c@x~8l Llrtt It 0(;',!,"')'GiwoiS:.':~,>>'>>",."."~)'k4Ni
':,;.'Aspera'ge,::Phriat;,,;,':'.g,.K:.'::.'::,1',HGR;:".:,-"..:.'.
!0.0 11.32 7.0 11.98 35.0 10.82 0.2 1.0 2.0 3.0 4.0 5.0 6.0 11.33 11.40 11.50 11.61 11.73 11.86 11;93 8.0 9.0 10.0 12.5 15.0 20.0 25.0 12.03 12.11 12.19 12.34 12.47 12.58 12.03 43.52 9.17 Ii'I e TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 17 15 14 13 12'Figure S APLHGR Limits for Bundle Type BP8DRBZ99 (BP8X8R)UNACCEPTABLE OPERATION 10 ACCEPTA BLE OPERAT ION 4 3'0.0 5.0 10.0 15.0 20.0 25.0 30.0 Cycle Exposure (GWD/ST)35.0 40.0:;'!i'::::::::-'.::Eppes'tl're':::.'.-;:>:;:.'::.,"',.".,:,"'.:.':.,:":.',":f imit";-.t:,"'.
)K.k'0:;Eltp0$ttfe jNK@j~c@x~8l LlrttIt 0(;
:::;.,::Average'.Planar'.-".-."$
',!,"')'GiwoiS:.':~,>>'>>",."."~)'k4Ni !
<-'"''ILHGR;
0.0 11.32 7.0 11.98 35.0 10.82 0.2 1.0 2.0 3.0 4.0 5.0 6.0 11.33 11.40 11.50 11.61 11.73 11.86 11;93 8.0 9.0 10.0 12.5 15.0 20.0 25.0 12.03 12.11 12.19 12.34 12.47 12.58 12.03 43.52 9.17
~j~.:~IAvemge::Planar:;~g'."::,LHGRmP 0.0 0.2 1:0 2.0 3.0 4.0 5.0 6.0 10.7.1 10.75 10.86 11.01 11.19 11.35 11.47 11.62, 7.0 8.0 9.0 10.0 12.5 15.0 20.0 25.0 11;78 11.95 12.09 12.20 12.37 12.47 12.37 11.77 35;0 r42 13 10.65 9.36  
 
.0 TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 18 Figure 9 Power DeyentIent MAPLHGR Factor-MAPFAC(P)1.2 0.8<50%Coro Flow O+os 0.4-0.2 I I I>>50%Core Row I I I I I 0 10 20 30 40 50 60 70 80 90 100 Power (%Rated)MAPLHGR(P)
Ii
=MAPFAC(P)x MAPLHGRstd.
'I e
MAPLHGRstd
 
=Standard MAPLHGR Limits For 30%<P For 25%>P: NO THERMAL LIMITS MONITORING REQUIRED For 25%<P<30%: MAPFAC(P)=0.60+0.005(P40%)
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 17 15 14 13 12' Figure S APLHGR Limits for Bundle Type BP8DRBZ99 (BP8X8R)
For<50%CORE FLOW: MAPFAC(P)=0.46+0.005(P-30%)
UNACCEPTABLEOPERATION 10 ACCEPTABLE OPERATION 4
For>50%CORE FLOW: MAPFAC(P)=1.0+0.005224(P-100%)
3' 0.0 5.0 10.0 15.0 20.0 25.0 30.0 Cycle Exposure (GWD/ST) 35.0 40.0
These values bound both Turbine Bypass InService and Out<fervice 0 4l TVA Nuclear Fuel Core Operating Limits Rcport TVA-COLR-BF2C10 Revision 0, Page 19 Figure 10 Flow.Dependent.
:;'!i'::::::::-'.::Eppes'tl're':::.'.-;:>:;:.'::.,"',.".,:,"'.:.':.,:":.',":fimit";-.t:,"'.
MAPLHGR Factor-MAPFAC(F)MAX FLOW<102.5%0.9 0.8 O M..0.7 MAX FLOW~1071L 0.6 0.5 0.4 30 60 70 Core Flow ('/i Rated)80 MAPLHGR(F)
:::;.,::Average'.Planar'.-".-."$ <-'"''ILHGR;~j~.:~IAvemge::Planar:;~g'."::,LHGRmP 0.0 0.2 1:0 2.0 3.0 4.0 5.0 6.0 10.7.1 10.75 10.86 11.01 11.19 11.35 11.47 11.62, 7.0 8.0 9.0 10.0 12.5 15.0 20.0 25.0 11;78 11.95 12.09 12.20 12.37 12.47 12.37 11.77 35;0 r42 13 10.65 9.36
=MAPFAC(F)x MAPLHGRstd MAPLHGRstd
 
=Standard MAPLHGR Limits MAPFAC(F)=MINIMUM(1.0, Af*Wc/100+Bf)Wc=%Rated Core Flow Af'and Bf are Constants Given Below: 102.5 107.0 0.6784 0.6758 0.4861 0.4574 These values bound both Turbine Bypass In<ervice and Out<service.
.0
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).
 
II 0 t TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 20 Figure 11.MCPR Operating Limit for GE13 1.42 1.41 Pl 1.4 O o 1.39.N 1.38 g 1.37<1.38 C.O 1.35 Turbin e Bypass 0 ut&f<ervi ce Turbine Bypass In<ervlce 1.34 1.33 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Option B Option A Tau (z).:'',",,Exjios'ice,';Rartge".:i
TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 18 Figure 9 Power DeyentIent MAPLHGRFactor - MAPFAC(P) 1.2 0.8
.;,"'..",.!OQt-'.Of'dijfci""..<:,".,':"$:;Option''.A-.:;."';::
< 50% Coro Flow O+os 0.4
g~;.:;:0'ptfciti::B'gg!
-0.2 I
BOC10 to EOC10 BOC10 to EOC10 na Turbine B ass 1.37 1 1.41 1.34 1.38 Notes 1.Use this value at BOC10 prior to performing scram time testing.
I I
0 4 TVA Nuclear Fuel Core Operating Limits Rcport TVA-COLR-BF2C10 Revision 0, Page 21 Figure 12 MCPR Operating, Limit for GE11 1.42 ED CI 1.41 ,1.4 O 1.39'.E 1;38 1.37 1.36 O Z 1.35 Tu rbine Byp ass Out&service Turbine Bypass!n Nervlce 1.33 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 10 Option B Option A Tau (q):.;.:,IKjp'aSttri,::,Range:'5':+gz
>> 50% Core Row I
+Pzvx~" i;':i%;:,'OC10to EOC10 ,'':,gttt&fpeiVIce>,'',.'".
I I
na 1.35 1 1.34:;ij:::O'Ation".::A'>'.,.:i.:
I I
+~>OPtiorINB!.',;t.:.,'OC10 to EOC10 Turbine B ass 1.39 1.36 Notes 1.Use this value at BOC10 prior to performing scram time testing.
0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)
0 II t TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 22 Figure 13 MCPR Operating Limit for GE9B (GE8X8NB)1.39 C 1.37'o O I 1'.36 E g 1.35 0 rc 1.34 O urblne Byp ass Outf Turbln e Bypass InService 1.32 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.6 0.9 1 Option B Option A Tan (q),'-,'',,Ojitiort;A:
MAPLHGR(P) = MAPFAC(P) x MAPLHGRstd.
g,::;.'.j':,':,pption::BI:':;.,;"':.'"Tits'=...1 0'."-;":"..-r'",.Ti'ti=;0;Oj":";.:,,', BOC10 to EOC10 na 1.34 1 1.34 BOC10to EOC10 Turbine B ass 1.36 1.34 Notes 1.Use thh value at BOC10 prior to performing scram time testing.
MAPLHGRstd = Standard MAPLHGRLimits For 30% < P For 25% >P:
0 iy TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 23 Figure 14 MCPR Operating Limit for GE7B (BP8XSR)1.39 1.38 1.37 O s 1.36 E g 1.35 1.34 0 O Turbine Bypass In<ervice 8 Outf&ervlce 1.32 0 0.1 0.2 , 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Option B Option A Tau (z).;:;Sxp'os'ure;.:Ra'ng'e;,;:;;;:
NO THERMALLIMITSMONITORING REQUIRED For 25% < P < 30%: MAPFAC(P) =0.60+ 0.005(P40%)
For <
50% CORE FLOW
: MAPFAC(P) = 0.46+ 0.005(P-30%)
For >
50% CORE FLOW
: MAPFAC(P) = 1.0 + 0.005224(P-100%)
These values bound both Turbine Bypass InService and Out<fervice
 
0 4l
 
TVANuclear Fuel Core Operating Limits Rcport TVA-COLR-BF2C10 Revision 0, Page 19 Figure 10 Flow.Dependent. MAPLHGRFactor - MAPFAC(F)
MAXFLOW < 102.5%
0.9 0.8 O
M..0.7 MAXFLOW ~ 1071L 0.6 0.5 0.4 30 60 70 Core Flow ('/i Rated) 80 MAPLHGR(F) = MAPFAC(F)x MAPLHGRstd MAPLHGRstd = Standard MAPLHGR Limits MAPFAC(F) = MINIMUM(1.0,Af*Wc /100+ Bf)
Wc =% Rated Core Flow Af'and Bfare Constants Given Below:
102.5 107.0 0.6784 0.6758 0.4861 0.4574 These values bound both Turbine Bypass In<ervice and Out<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).
 
II 0
 
t TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 20 Figure 11
. MCPR Operating Limitfor GE13 1.42 1.41 Pl 1.4 O
o 1.39
.N 1.38 g 1.37
< 1.38 C.
O 1.35 Turbine Bypass 0ut&f<ervice Turbine Bypass In<ervlce 1.34 1.33 0
0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1
Option B Option A Tau (z)
.:'',",,Exjios'ice,';Rartge".:i.;,"'..",.!OQt-'.Of'dijfci""..<:,
".,':"$:;Option''.A-.:;."';:: g~;.:;:0'ptfciti::B'gg!
BOC10 to EOC10 BOC10 to EOC10 na Turbine B ass 1.37 1
1.41 1.34 1.38 Notes
: 1. Use this value at BOC10 prior to performing scram time testing.
 
0 4
 
TVANuclear Fuel Core Operating Limits Rcport TVA-COLR-BF2C10 Revision 0, Page 21 Figure 12 MCPR Operating, Limitfor GE11 1.42 ED CI 1.41
,1.4 O
1.39
.E 1;38 1.37 1.36 OZ 1.35 Turbine Bypass Out&service Turbine Bypass!n Nervlce 1.33 0
0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 10 Option B Option A Tau (q)
:.;.:,IKjp'aSttri,::,Range:'5':+gz +Pzvx~" i; ':i%;:,
'OC10to EOC10
,'':,gttt&fpeiVIce>,'',.'".
na 1.35 1
1.34
:;ij:::O'Ation".::A'>'.,.:i.:
+~>OPtiorINB!.',;t.:.,'OC10 to EOC10 Turbine B ass 1.39 1.36 Notes
: 1. Use this value at BOC10 prior to performing scram time testing.
 
0 II
 
t TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 22 Figure 13 MCPR Operating Limitfor GE9B (GE8X8NB) 1.39 C 1.37
'oO I
1'.36 E
g 1.35 0
rc 1.34 O
urblne Bypass Outf Turblne Bypass InService 1.32 0
0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.6 0.9 1
Option B Option A Tan (q)
,'-,'',,Ojitiort;A:
g,::;.'.j':,':,pption::BI:':;.,;"':.'"Tits'=...1 0'."-;":"..- r'",.Ti'ti=;0;Oj":";.:,,',
BOC10 to EOC10 na 1.34 1
1.34 BOC10to EOC10 Turbine B ass 1.36 1.34 Notes
: 1. Use thh value at BOC10 prior to performing scram time testing.
 
0
 
iy TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 23 Figure 14 MCPR Operating Limitfor GE7B (BP8XSR) 1.39 1.38 1.37 O
s 1.36 E
g 1.35 1.34 0
O Turbine Bypass In<ervice 8 Outf& ervlce 1.32 0
0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Option B Option A Tau (z)
.;:;Sxp'os'ure;.:Ra'ng'e;,;:;;;:
BOC10 to EOC10 BOC10 to EOC10 F,".;,iOttt&fpeptice~;;,~
BOC10 to EOC10 BOC10 to EOC10 F,".;,iOttt&fpeptice~;;,~
na Turbine B ass 1.34 1 1.34 1.34 1.34 Notes 1.Use this value at BOC10 prior to performing scram time testing.
na Turbine B ass 1.34 1
II-J F TVA Nuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 24 Figure 15 Power Dependent MCPR(P)Limits 3.2 I i50II FLOW(TSOOS)
1.34 1.34 1.34 Notes
CL IO EO cO o a.A O.,O'h 0 O oN 0 R O.g 0 O 0 0 Eg 2.8 2.6 2.4 2.2 1.8 1.6 1.4 1.2<<50%FLOW (raoos)0 10 20 30 40 50 60 70 80 90 100 Power (%Rated)OPERATING'LIMIT MCPR P=K'LMCPR 100 For P<25%: NO THERMAL LIMITS MONITORING REQUIRED For 25%<P<Pbypass:(Pbypass=30%): Kp=[Kbyp+0.02(30%-P)]/OLMCPR(100)
: 1. Use this value at BOC10 prior to performing scram time testing.
Turbine B ass In&ervice Kbyp=1.97 For<50%CORE FLOW Kbyp=2.21 For>50%CORE FLOW Turbine B ass Out-Of&ervice Kbyp=2.01 For<50%CORE FLOW Kbyp=3.01 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)
II
: Kp=1.00+0.00375(100%-P)
-J
Ik 4l TVA Nuclear.Fuel Core Operating Limits Report TVA-COLR-BF2C10'evision 0, Page 25 (Final)Figure 16 Floxv Dependent MCPR Operating Limit-MCPR(F)1.'6 1.5.1.4 MAX FLOW<107'4 1.3 MAX FLOW i 102.0~/1.2 30 70 core Flow (%Rated)For Wc<40%For.Wc>40%: MCPR(F)=(Af'Wcl100+
 
Bf)'[1+0.0032(40-Wc)]
F TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 24 Figure 15 Power Dependent MCPR(P) Limits 3.2 I
:.MCPR(F)~MAX(1.23, Af'Wcl100+
i50IIFLOW(TSOOS)
Bf)Wc~%Rated Core Flow Af and Bf are Constants Given Below: , l",:gaximunt%
CL IO EO cO o a.
,'<Cere',FfoIhr~
A O.,O
!$:::.li:Raated;5'02.5 1.701 107.0%.603 1.745 These values bound both Turbine Bypass InZervice and Out-OfZervlce.
'h 0
The 102.5%maximum flow line ls used for operation up to 100%rated, flow.The 107%maximum flow line ls used for operation up to 105%rated flow (ICF).
O oN0 R O.
g 0 O0 0 Eg 2.8 2.6 2.4 2.2 1.8 1.6 1.4 1.2
<<50% FLOW(raoos) 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
:(Pbypass = 30%)
: Kp = [Kbyp+ 0.02(30%-P)]/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&ervice Kbyp = 2.01 For <
50% CORE FLOW Kbyp=3.01 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)
 
Ik 4l
 
TVANuclear. Fuel Core Operating Limits Report TVA-COLR-BF2C10'evision 0, Page 25 (Final)
Figure 16 Floxv Dependent MCPR Operating Limit-MCPR(F) 1.'6 1.5
.1.4 MAXFLOW < 107'4 1.3 MAXFLOWi 102.0~/
1.2 30 70 core Flow (% Rated)
For Wc
< 40%
For.
Wc 40%
: MCPR(F) = (Af'Wcl100+ Bf)'[1+0.0032(40-Wc)]
:. MCPR(F) ~ MAX(1.23,Af'Wcl100+ Bf)
Wc ~% Rated Core Flow Afand Bfare Constants Given Below:
,l",:gaximunt%
,'< Cere',FfoIhr~
!$:::.li:Raated;5'02.5 1.701 107.0
%.603 1.745 These values bound both Turbine Bypass InZervice and Out-OfZervlce.
The 102.5% maximum flow line ls used for operation up to 100% rated, flow.
The 107% maximum flowline ls used for operation up to 105% rated flow (ICF).
 
il..}}
il..}}

Latest revision as of 11:26, 6 January 2025

Cycle 10 Colr
ML18038B973
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 09/26/1997
From: Bruce A, Keys T, Riley E
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18038B972 List:
References
TVA-COLR-BF2C10, TVA-COLR-BF2C10-R, TVA-COLR-BF2C10-R00, NUDOCS 9710210148
Download: ML18038B973 (50)
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Text

t TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision.0, 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, Engineering Specialist BWR Fuel Engineering Da~e:

Verified By Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering

.Approved By:

T; A.'Keys, Ma ger BWR Fuel Engineering Date Reviewed By:

eactor Engineering Supervisor Date:

Reviewed. By:

PORC Chairman Date:

97i02iOi48 9'7iOi5 PDR ADQCK 050002bO P

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l TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 2 Revision Log Revision Date 0

9/25/97 D~escri tion InitialRelease AfFected Pa es All

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1 TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 3'.INTRODUCTION This Core Operating Limits Report for Browns: Ferry Unit 2, Cycle 10 is prepared in accordance with the requirements ofBrowns 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'.S.I)

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.l.c and Table 3.2:C)

e. Rod Block Monitor (RBM) Trip Setpoints (Technical, Specification Table 3.2:C)

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision'0, Page 4

,2. APLHGRLIMIT(TECHNICALSPECIFICATION 3.5."I)

The APLHGR limits for fullpower 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 flow-adjusted value is taken as. the APLHGR operating limitfor, the ofF-rated condition.

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page'5

3. LHGRLIMIT(TECHNICALSPECIFICATION 3.5.J)

The LHGR limitfor unit 2 cycle 10 is fuel type dependent, as shown below:

GE7B (BP8X8R) 13.4 kw/ft 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 Report TVA-COLR-BF2C10 Revision 0, Page 6 4; OLMCPR (TECHNICALSPECIFICATION 3.5.K/4.5.K)

.a.

The MCPR Operating Liinitfor rated power and flow 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:

= 0.0 Zme ZB of ZA ZB whichever is greater.

'5 = 0.90 sec (Specification 3.3.C. 1 scram time limitto 20%

insertion from fullywithdrawn )

i Z~ = 0.710 + 1.65 (0.053)

N

~

n ng zi i=i Zave n

where; n = Number ofsurveillance rod tests'performed to date in cycle (including BOC test).

Zi = Scram time to 20% insertion from fullywithdrawn of.the i foil.

N = Total. number of active 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),

'6 = 1.0 c.

For the performance ofSurveillance 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 of-rated condition.

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TVANuclear Fuel Core Operating LimitsReport'VA-COLR-BF2C10 Revision 0, 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 5 (0;66W+66Ão)

SRB g (0 66W + 64')

Allowable Value Nominal Trip Setpoint (NTSP) where:

SRB.=:Rod Block setting in percent ofrated thermal power (3293 MWt)

W = Loop recirculation flow rate in percent ofrated The APRM Rod Block trip setting is clamped at a maximum allowable value of 115 jo (corresponding to a NTSP of 113/o).

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TVANuclear Fuel Core Operating Limits Rcport TVA-COLR-BF2C10 Revision 0, Page 8

6. ROD BLOCKMONITOR(RBM) TRIP SETPOINTS (TECHNICALSPECIFICATION TABLE3.2.C)

The RBM trip setpoints and applicable power ranges, shall be as follows:

LPSP 27%

25%

IPSP 62o/

60%

HPSP 82%

80%

LTSP - unfiltered

- filtered, 121 7%

120.7%

120 0%

119 0%

(1) (2)

ITSP - unfiltered

- filtered 116.7%

115.7%

115.0%

114.0%

(1) (>)

HTSP - unfiltered

- filtered.

111.7%

1.10.9%

110.0%

109.2%

(1) (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 of0.0 seconds (reference 8). The filtered setpoints are consistent with a nominal RBM filter setting < 0.5 seconds (reference 7).

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, 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. Jl 1-03144SRL'R Rev. 1, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 2 Reload 9 Cycle 10", September 1997.
4. Jl 1-03:144MAPL 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, "MaximumExtended Load Line Limit-and 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 Authority Browns 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 Authority Browns Ferry Nuclear Plant", dated, Sept. 1997.

9. GE Letter LBAt: 262-97-133, "Browns Ferry Nuclear Plant Rod Block Monitor Setpoint Clarification - GE Proprietary Information", dated September 12, 1997.

,[L32 970912 800]

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 10 15 14 13 Figure 1 APLHGR Limits for Bundle Type GE13-P9HTB384-12G4.0 (GE13) 12.

UNACCEPTABLE OP ERATION 10 9

,8 lY 7

(o o.

6 ACCEPTABLE OPERATION 0

0 0 10.0 20.0 30.0 Cycle Exposure (GWDIST) 40.0 50.0

AVe'rage::Plai1arp,":.:'::i,,:,."L'HGR::;-;!:;:i);;

",>".';;:.:",'.;.Ei'Pastire'.:::,":,::;,:'.I:;,::-;'::;:-:I.'im'i':,.':.;

Most Limiting Lattice for Each Exposure Point

,::; Ave'raqe,:P.lanai~~:.;.:::;::,'I HGR;:;"Si ':,;Average'.,Planar)~::-;::L'HGR"~

0.0 0.2 1.0 2.0 3.0 4.0 10.09 10.15 10.31 10.52 10.75 10.99 7.0 8.0 9.0 10.0 12.5 15.0 11.71 11.95 12.16 12.28 12.16 11.88 25.0 30.0 35.0 40.0 45.0 50.0 10.6 9.99 9.39 8.76 8.11 7.44 5.0 6.0 11.25 11.48 17 51.1.56 20.0 11.24 55.0 55.98 6.60

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-'BF2C10 Revision 0, Page 11 Figure 2 APLHGR Limits for Bundle Type GE11-P9HUB366-12G4.0 (GE11) 15 14 13 12 UNACCEPTABLE OPERATION 10 p

9 8

E, 7

U o.

6 5

I 4

ACCEPTABLE OPERATION 0

0 0 10.0 20.0 30.0 Cycle Exposure (GWDIS'f) 40.0 50.0

Avera'ge.
.:Pla'vari,::::::::,';.:,":,:.;".,::ILHGR(':,::.:,'

'j~-.;j.EXji0S4rP ~:;-"~~"'~:;;(jib,imit;;-'(;;;',':

!'
::, 6WDIS.::":-;::;:::::,:.:';,',::"::::,":::.kwlft:,":

Most Limiting Lattice for Each Exposure Point

';;,":Averige':.;Plariar",',::,:::,'-:.:::.:;,':.".:L'HGR:::;.":

'.'!.'""A"GWDIS

:>"."I'c."."':i""'$ft

!:"Average Plaiiar@k5'.:::LHGRP~

'0.0 0.2 1.0 9.55 9.62 9.80 7.0 11.39 8.0 11.67 9.0 11.81 30.0 9.84 35.0 9.19 25.0 10.51 2.0 3.0 4.0 5.0 6.0 10.05 10.32 10.58 10.84 10.0 12.5 15.0 17.5 20.0 11'.95 11.92 11.72 11.48 11.20 40.0 45.0 50.0 55.0 56.17 8.55 7.91 7.26 6.59 6.42

41

TVANuclear Fuel Core Operating LimitsRcport TVA-COLR-BF2C10 Revision 0, Page 12 Figure,3 APLHGR Limits for Bundle Type GE11-P9HUB367-14GZ (GE11) 15 14 13 UNACCEPTABLE OPERATION 10 9

8 7

ts' 5

ACCEPTABLE OPERATION

,3 0

0 0 10.0 20.0 30.0 Cyme Exposure (GWDIST) 40.0 50.0

~A'aerage;
,PIanii.':.:,':,~F(!:-::.'ILHGR:,",.;:.j:;
<
:::;"',,BXfiostirA";:I:;:,:::>>;.:;;-.;,:,';;;:::::Limit;,:,::,":;.;

'.4!'= GIND'18

.,';:.:;.:-;:":"'..'; 6'ih:,-::-":.:

Most Limiting Lattice for Each Exposure Point

!Average
:Planar~"';:'lHGR(j 0.2 9;27 1.0 9.45 9.'72 2.0 0.0 9.18 7.0'.0 9.0 10.0 11.31 11.67 11.81 11.95 25.0 30.0 35.0 40.0 10.51 9.84 9.19 8.55 3.0 4.0 5.0'.0 10.00 10.30 10.62

.10.95 12.5 15.'0 17.5 20.0 1,1;92 11.72 1'1.48 11.20 45.0 50.0 55.0 56.17 7.91 7.26 6.59 6.42

ih 4l>>

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 13

'Figure 4 APLHGR Limits for Bundle Type GE9B-PSDWB319-9GZ (GESXSNB) 15 14 13 12 UNACCEPTABLEOPERATION 10 9

8 E

7 U

o.

'6 5

ACCEPTABLE OPERATION 4

0 0.0 10.0 20.0 30.0 Cycle Exposure (GWDIST) 40.0 50.0

,;",'
EIt'P0SMri~
;
,
;:.".,';:;",':::,:,,",:.','.;.Limit>>:,'-.",'.-:.:

Most Limiting Lattice for Each Exposure Point

';";,'Averige':Planar-::.:::,"'."".K'Ak':HGRg:;-.'";;:;'.-,:,'Ayera'ge::Planar Sg"':::,LHSR@m

'.".-':< Geois

<l..':""::..':::.>> itWe;<>>::.'::.>>~ GWDIS..";k:<4k@VIft;.

0.0 11.64 11.68 0.2 1.0 11;77 7.0 12.49 8.0 12.65 12.77 9.0 35.0 10.41 45.0 8.81 51.2 5.91 2.0 3.0 4.0 5.0 6.0 11.88 12.01 12.'12 12.'22 12.32 10.0 12.5 15.0 20.0

'25.0 12.86 12.86 12.62 12.06 11.47

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TVANuclear Fuel Core Operating Limits Report

'VA-COLR-BF2C10'evision 0, Page 14

.15 14 1312'BLE OPERATIO UNACCEPT Figure 5 APLHGR Limits for Bundle Type GE9B-P8DWB325-10GZ (GE8XSNB) 10 9

8 E

7 (ox o.

6 ACCEPTABLE OPERATION 4

0 00'0.0 20.0 30.0 Cycle Exposure (GWDISTI 40.0 50.0 Most Limiting Lattice for Each Exposure Point

-AVera96::PJaltarjj,.-:,:...jLHGR.:'!.:':::'::,'j'Average'::Planar"',.',>>.".":I;."-",;L'HGR~:,

'Qa":Planar'~:.='.;.".:'.LHGR@

0.2 11.00 1.0 11.11 0.0 10.97 7.0 12.23 12.46 9.0 8.0 12.35 35.0 45.0 50.27 10.12 8.60 5.92 2.0 3;0 4.0 5.0 6.0 11.31 11.54 1-1.79 11.97 12.10 10.0 12.5 15.0 20.0 25.0 12.58 12.58 12.35 11.86 11.33

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-'BF2C10 Revision 0, Page 15 15 14 Figure 6 APLHGR Limits for Bundle Type GE9B-PSDWB326-7GZ (GE8X8NB) 13 12.

UNACCEPTABLE'OPERATION 10 9

E 8

7 U'.

6 5

ACCEPTABLE OPERATION 3

0

.0 0 10.0 20.0 30.0 Cyde Exposure (GWD/ST) 40.0

. Av'clay'e::Planar,,;';,'g.::::.'.;::.LHGR;":.::::":;.',?

,:.,i',:i!!i'Ntf)IS'T,'i!i:.'":i:::.k$

l':,'.-'.:'; tei'ilft'i" ":

Most Limiting Lattice for Each Exposure Point

'
,'Avera9e;PIartar'-:;::.:,

~.;:: LHGR:::;',': :;"."Averar'Ie::Pfatla'r,,:;.'.';>j'.::,LHGR;g

~:

,'."'GWDI8T. S.".'5Nh>>

ki7iilft,"..'.0 0.2 1.0 11;45 11.47 11;55 7.0 8.0 9.0 12.31 12.41 12.51 35.0 45.0 50.49 10.15 5.93 2.0 11.70 10.0 12.63 3.0 11.87 12.5 12.64 4.0 12.01 15.0 12.41 5.0 6.0 12.13 12.22 11.35 25;0 20.0 11.91

If

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 16 Figure 7 APLHGR Limits for Bundle Type BP8DRB301L (BP8X8R) 15 14 13 12 UNACCEPTABLE OPERATION 10 8

E 7

U ABLEOP ACCEPT ERATION 0

0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 Cyde Exposure (GWDIST)

';,IAVersgj;Pjariar:,'";,.;"..::.',",:>,.l-,;;;:l.'HOT;,".,'.:

.'-':;:.'::-."'GV'io'is

'""M:.3'.".':::.;'kwi8:J.":

':,;.'Aspera'ge,::Phriat;,,;,':'.g,.K:.'::.'::,1',HGR;:".:,-"..:.'.

)K.k'0:;Eltp0$ttfe jNK@j~c@x~8l LlrttIt 0(;

',!,"')'GiwoiS:.':~,>>'>>",."."~)'k4Ni !

0.0 11.32 7.0 11.98 35.0 10.82 0.2 1.0 2.0 3.0 4.0 5.0 6.0 11.33 11.40 11.50 11.61 11.73 11.86 11;93 8.0 9.0 10.0 12.5 15.0 20.0 25.0 12.03 12.11 12.19 12.34 12.47 12.58 12.03 43.52 9.17

Ii

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 17 15 14 13 12' Figure S APLHGR Limits for Bundle Type BP8DRBZ99 (BP8X8R)

UNACCEPTABLEOPERATION 10 ACCEPTABLE OPERATION 4

3' 0.0 5.0 10.0 15.0 20.0 25.0 30.0 Cycle Exposure (GWD/ST) 35.0 40.0

'!i'
:::::::-'.::Eppes'tl're':::.'.-;:>:;:.'::.,"',.".,:,"'.:.':.,:":.',":fimit";-.t:,"'.
.,
:Average'.Planar'.-".-."$ <-'"ILHGR;~j~.:~IAvemge::Planar:;~g'."::,LHGRmP 0.0 0.2 1:0 2.0 3.0 4.0 5.0 6.0 10.7.1 10.75 10.86 11.01 11.19 11.35 11.47 11.62, 7.0 8.0 9.0 10.0 12.5 15.0 20.0 25.0 11;78 11.95 12.09 12.20 12.37 12.47 12.37 11.77 35;0 r42 13 10.65 9.36

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TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 18 Figure 9 Power DeyentIent MAPLHGRFactor - MAPFAC(P) 1.2 0.8

< 50% Coro Flow O+os 0.4

-0.2 I

I I

>> 50% Core Row I

I I

I I

0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)

MAPLHGR(P) = MAPFAC(P) x MAPLHGRstd.

MAPLHGRstd = Standard MAPLHGRLimits For 30% < P For 25% >P:

NO THERMALLIMITSMONITORING REQUIRED For 25% < P < 30%: MAPFAC(P) =0.60+ 0.005(P40%)

For <

50% CORE FLOW

MAPFAC(P) = 0.46+ 0.005(P-30%)

For >

50% CORE FLOW

MAPFAC(P) = 1.0 + 0.005224(P-100%)

These values bound both Turbine Bypass InService and Out<fervice

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TVANuclear Fuel Core Operating Limits Rcport TVA-COLR-BF2C10 Revision 0, Page 19 Figure 10 Flow.Dependent. MAPLHGRFactor - MAPFAC(F)

MAXFLOW < 102.5%

0.9 0.8 O

M..0.7 MAXFLOW ~ 1071L 0.6 0.5 0.4 30 60 70 Core Flow ('/i Rated) 80 MAPLHGR(F) = MAPFAC(F)x MAPLHGRstd MAPLHGRstd = Standard MAPLHGR Limits MAPFAC(F) = MINIMUM(1.0,Af*Wc /100+ Bf)

Wc =% Rated Core Flow Af'and Bfare Constants Given Below:

102.5 107.0 0.6784 0.6758 0.4861 0.4574 These values bound both Turbine Bypass In<ervice and Out<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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t TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 20 Figure 11

. MCPR Operating Limitfor GE13 1.42 1.41 Pl 1.4 O

o 1.39

.N 1.38 g 1.37

< 1.38 C.

O 1.35 Turbine Bypass 0ut&f<ervice Turbine Bypass In<ervlce 1.34 1.33 0

0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1

Option B Option A Tau (z)

.:,",,Exjios'ice,';Rartge".:i.;,"'..",.!OQt-'.Of'dijfci""..<:,

".,':"$:;Option.A-.:;."';:: g~;.:;:0'ptfciti::B'gg!

BOC10 to EOC10 BOC10 to EOC10 na Turbine B ass 1.37 1

1.41 1.34 1.38 Notes

1. Use this value at BOC10 prior to performing scram time testing.

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TVANuclear Fuel Core Operating Limits Rcport TVA-COLR-BF2C10 Revision 0, Page 21 Figure 12 MCPR Operating, Limitfor GE11 1.42 ED CI 1.41

,1.4 O

1.39

.E 1;38 1.37 1.36 OZ 1.35 Turbine Bypass Out&service Turbine Bypass!n Nervlce 1.33 0

0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 10 Option B Option A Tau (q)

.;.:,IKjp'aSttri,::,Range:'5':+gz +Pzvx~" i; ':i%;:,

'OC10to EOC10

,:,gttt&fpeiVIce>,,.'".

na 1.35 1

1.34

ij
::O'Ation".::A'>'.,.:i.:

+~>OPtiorINB!.',;t.:.,'OC10 to EOC10 Turbine B ass 1.39 1.36 Notes

1. Use this value at BOC10 prior to performing scram time testing.

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t TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 22 Figure 13 MCPR Operating Limitfor GE9B (GE8X8NB) 1.39 C 1.37

'oO I

1'.36 E

g 1.35 0

rc 1.34 O

urblne Bypass Outf Turblne Bypass InService 1.32 0

0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.6 0.9 1

Option B Option A Tan (q)

,'-,,,Ojitiort;A:

g,::;.'.j':,':,pption::BI:':;.,;"':.'"Tits'=...1 0'."-;":"..- r'",.Ti'ti=;0;Oj":";.:,,',

BOC10 to EOC10 na 1.34 1

1.34 BOC10to EOC10 Turbine B ass 1.36 1.34 Notes

1. Use thh value at BOC10 prior to performing scram time testing.

0

iy TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 23 Figure 14 MCPR Operating Limitfor GE7B (BP8XSR) 1.39 1.38 1.37 O

s 1.36 E

g 1.35 1.34 0

O Turbine Bypass In<ervice 8 Outf& ervlce 1.32 0

0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Option B Option A Tau (z)

.;:;Sxp'os'ure;.:Ra'ng'e;,;:;;;:

BOC10 to EOC10 BOC10 to EOC10 F,".;,iOttt&fpeptice~;;,~

na Turbine B ass 1.34 1

1.34 1.34 1.34 Notes

1. Use this value at BOC10 prior to performing scram time testing.

II

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F TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 0, Page 24 Figure 15 Power Dependent MCPR(P) Limits 3.2 I

i50IIFLOW(TSOOS)

CL IO EO cO o a.

A O.,O

'h 0

O oN0 R O.

g 0 O0 0 Eg 2.8 2.6 2.4 2.2 1.8 1.6 1.4 1.2

<<50% FLOW(raoos) 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

(Pbypass = 30%)
Kp = [Kbyp+ 0.02(30%-P)]/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&ervice Kbyp = 2.01 For <

50% CORE FLOW Kbyp=3.01 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)

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TVANuclear. Fuel Core Operating Limits Report TVA-COLR-BF2C10'evision 0, Page 25 (Final)

Figure 16 Floxv Dependent MCPR Operating Limit-MCPR(F) 1.'6 1.5

.1.4 MAXFLOW < 107'4 1.3 MAXFLOWi 102.0~/

1.2 30 70 core Flow (% Rated)

For Wc

< 40%

For.

Wc 40%

MCPR(F) = (Af'Wcl100+ Bf)'[1+0.0032(40-Wc)]
. MCPR(F) ~ MAX(1.23,Af'Wcl100+ Bf)

Wc ~% Rated Core Flow Afand Bfare Constants Given Below:

,l",:gaximunt%

,'< Cere',FfoIhr~

!$:::.li:Raated;5'02.5 1.701 107.0

%.603 1.745 These values bound both Turbine Bypass InZervice and Out-OfZervlce.

The 102.5% maximum flow line ls used for operation up to 100% rated, flow.

The 107% maximum flowline ls used for operation up to 105% rated flow (ICF).

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