ML18039A736

Rev 4 to TVA-COLR-BF2C10, Bfnp,Unit 2,Cycle 10 Colr

ML18039A736
Person / Time
Site:	Browns Ferry
Issue date:	03/11/1999
From:	Bruce A, Keys T, Riley E TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18039A735	List: ML18039A733 ML18039A736
References
TVA-COLR-BF2C10, TVA-COLR-BF2C10-R04, TVA-COLR-BF2C10-R4, NUDOCS 9904060139
Download: ML18039A736 (52)

Text

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 4, 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:

Verified By:

Earl E. Riley, 'Engin ring Specialist BWR Fuel Engineering Qc 44Lc~

Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering Date:

>/~Yt'e Approved By:

T. A. Keys, anager BWR Fuel Engineering Date:

Reviewed'y:

Reactor Engineer' Supervisor Date:

> t'/~i Reviewed By:

PORC Chairman Revision 4 (3/10/1999)

Extend MAPLHGRData for BP8DRB299 Bundle Pages Affected:

1, 2, 10, 18 iyqottoeoi'39 990~~+'DR ADOCK 050002bO PDR P

II.

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TVANuclear Fuel Core Operating Limits KPP6rt t

TVA-COLR-BF2C10 Revision 4, 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) 1, 2, 6, 9 7/8/98 Revise to Implement Improved Technical Specification Requirements All 1/27/99 Include Requirements for Single Loop Operation 1, 2, 4, 6-8, 10-18, 21-24 3/10/99 Extend MAPLHGRTable for BP8DRB299 Bundle 1,2, 10, 18

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TVANuclear Fuel Core Operating Limits~art TVA-COLR-BF2CI0 Revision 4, 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 5.6.5.

The core operating limits presented here were developed'sing NRC-approved methods (References 1 and 2).

Results from the reload analyses for Browns Ferry Unit 2, Cycle 10 axe.documented in Reference 3.

The following,core operating limits.are. included in'this. report:

a.

Average. Planar Linear Heat Generation Rate (APLHGR) L'imit (Technical Specifications 3.2.1 and 3.7.5)

b. Linear Heat Generation Rate (LHGR) Limit (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'pecification Table 3.3.2.1-1) f.

Shutdown. Margin.(SDM) Limit (Technical Specification 3.1.1)

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TVANuclear Fuel Core Operating LimitsR~rt t

TVA-COLR-BF2C10 Revision 4, Page 4

2. APLHGR LIMIT(TECHNICALSPECIFICATIONS 3.2.1 AND 3.7.5) 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 ~FAC(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.

The APL'HGR limits in figures 1-8 are applicable for both Turbine Bypass In-Service and Out-Of-Service. The off-rated power and flow corrections in figures 9 and 10 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 11). It is not necessary to apply both the off-rated MAPFAC and SLO multiplier corrections at the same time.

TVANuclear Fuel Core Operating Limits Ressort t

TVA-COLR-BF2C10 Revision 4, Page 5

3. LHGR LIMIT(TECHNICALSPECIFICATION 3.2.3)

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

Fuelype L'HGR 'Limit 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 Re~rt t

TV A-COLR-BF2C10 Revision 4, 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 Figures 11 thru 14.

As noted in Figures 11 thru 14, an adder of 0.02 is applied for single loop operation.

The actual OLMCPR(100) value i's dependent upon the scram time testing results, as described below:

'C = 0.0 or Cave CB whichever is greater where; 'C= 1.096 sec (analytical Option A scram time limit-based on dropout time for notch position 36) n Zr t

N 2

65 n'here; p =

O.S30 sec (mean scxam time used in txansient analysis-based on dropout time for notch position 36) cz =

0.019 sec (standard deviation of p)

N = Total numbex of active rods measured in Technical Specification Surveillance Requirement SR3.1.4.1 n = Number of surveillance rod tests performed to date in cycle

~; = 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-xated 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.

d.. OLMCPR limits.and off-rated corrections are provided for Recirculation Pump Txip out-of-service (RPTOOS) or Turbine Bypass out-of-service (TBOOS) conditions. These events are analyzed'separately and the coxe is not analyzed for both systems Out-Of-Service at the same time.

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TVA',Nuclear Fuel

'Core Operating'Limits R/6rt t

TVA-COLR-BF2C10 Revision 4, Page 7

5. APRM FLOW BIASED ROD BLOCKTRIP SETTING '(TECHNICAL

'EQUIREMENTS MANUA'LSECTION 5.3.1 AND TABLE3.3.4-1)

The APRM Rod Block trip setting shall be:

SRB 5 (0.66(W-bW) + '66%)

SRB 5 (0.66(W-bW) + 64%)

Allowable Value Nominal Trip Setpoint (NTSP) where:

Rod.Block setting in percent of rated thermal power (3293 MWt)

Loop recirculation flow rate in percent of rated Difference between two-loop and single-loop effective recirculation, flow at the same core flow (8 W=O.O for two-loop operation)

The APRM Rod Block trip setting is clamped'at a maximum allowable value of 115%

(corresponding to a NTSP of'1'13%).

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TVANuclear Fuel Core Operating Limits R~rt TVA-COLR-BF2C10 Revision 4, 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:

'RBMTrip Setpoint Allowable Value, 'ominal Trip.Setpoint (AV).,'

(NTSP)

LPSP IPSP HPSP LTSP - unfiltered

- filtered ITSP - unfiltered

- filtered 27%

62%

82%

121.7%

120.7%

116.7%

115.7%

25%

60%

80%

120.0%

119.0%

115.0%

114.0%

(t) (2)

(l),(2)

HTSP - unfiltered

- filtered DTSP 111.7%

110.9%

90%

110.0%

109.2%

92%

(l) (2)

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).

The RBM setpoints in Technical Specification Table 3.3.2.1-1 are applicable when:

THERMAL'OWER

(.% 'Rated)'pplicable

¹tes 'from MCPR +

I 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).

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'ore Operating Limits.~ort TVA-COLR-BF2C10 Revision 4, Page 9

7. SHUTDOWNMARGIN(SDM)'IMIT

'TECHNICAL,'SPECIFICATION3.1.1)

The. core shall be subcritical with the following margin with the strongest OPERABLE control rod fullywithdrawn and all other OPERABL'E control rods fully inserted.

,SDM > 0.'3S% dk/k

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TVANuclear Fuel Core Operating Limits R~c, ort TVA-COLR-8F2C10 Revision 4, Page 10

8. 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. J11-03144MAPL 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 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 LB¹: 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]

11. GE Letter LB¹262-98-111, "Browns Ferry Nuclear Plant Supplemental Reload Licensing Information for Unit 3 Cycle 8

Ec Unit 2 Cycle 10 - GE Proprietary Information", dated July 31, 1998.

12. GE Letter JEF:99-007, "Browns Ferry 2 Cycle 10 GE7B Peak Pellet Exposure Limit Extension", dated March 10, 1999.

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TVANuclear Fuel Core Operating Limits R~rt TVA-COLR-BF2C10 Revision 4, Page 11 I

2 Figure 1 APLHGR Limits for Bundle Type GE13-P9HTB384-12G4.0 (GE13) 15 14.

13.

12 NACCEPTABLE OP ERATIO 10 9.

8.

E 7.

UX 6

5 BLE OPERATIO CCEPTA 0.0 10.0 20.0 30.0 Cyclo Exposuro (GWO/ST) 40.0 50.0 verage~, anar '

iExposure

',L'imit (GWD/STi)..., ':I(kw/ft);

Most Umiting Lattice for Each Exposure Point veraget anar " '

'," veragei anar-iExposure iL'imlt. ',

Exposure'imit

,(GWD/ST~);

'kw'/ft)~ -"::(GWD/STI)'kw/ft)

These values apply to both Turbine Bypass In4ervice and Out-Of4ervlce.

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 I8$5rt I

TVA-COLR-BF2C10 Revision 4, Page 12 Figure 2 APLHGR Limits for Bundle Type GE11-P9HUB366-12G4.0 (GE11) 15 14 13-12.

ERATIO CEPTABLE OP NAC 10.

9 8

E 7

ts 6

5.

BLE OPERATIO CCEPTA 0

0 10.0 20.0 30.0 Cyclo Exposure (GWDIST) 40.0 50.0 Most Urniting Lattice for Each Exposure Point verage~

. anar

.veraget anar-iExposure,Limit-..

i -;

tExposure

'Llmlt-

'GWD/ST)

(kw'lft)

'.. '(GWD/ST~)

(kw/ft) verage anar

Exposure Limit (GWDIST~)

j(kw/ft)

These values apply to both Turbine Bypass InCervice and Out-OfNervice.

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~rt t

TVA-COLR-BF2C10 Revision 4, Page 13 Figure 3 APLHGR Limits for Bundle Type GE11-P9HUB367-14GZ (GE11) 15 14 13

~

12 CEPTABLE OPERATIO MAC 10 9.

8 E

cc 7

to 6-5.

BLE OPERATIO CCEPTA 0

0.0 10.0 20.0 30.0 Cycle Exposure (GWDISTI 40.0 50.0 veragei

. anar.

Expos'ure-

,(GWD/STi)

'Limit

,(kw/ft)

Most Umiting Lattice for Each Exposure Point

., veragei, anar Exposure iL'imlt (GWD/ST),

(kw/ft) veragei

. anar

'Exposure Limit

. (GWD/ST)

(kw/ft)

These values apply to both Turbine Bypass Inervice and Out-Of<ervice.

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.

0 0

TVANuclear Fuel Core Operating Limits RIPFrt t

TVA-COLR-BF2C10 Revision 4, Page 14 Figure 4 APLHGR Limits for Bundle Type GE9B-PSDWB319-9GZ (GE8X8NB) 15 14 13 12 TABLEOPERATlo NACCEP 10 8.

E IL 7

tox 6.

5.

E OPERATIO CCEPTABL 0

0 10.0 20.0 30.0 Cyclo Exposure (GWD/ST) 40.0 50.0 Most Limiting Lattice for Each Exposure Point verage:., anar. ;,,

veraget anar; verage anar

"'Exposure-

-,L'lmlt,,':Exposure

Limit.;'xposure Limit

,(GWD/ST)

~(kw/ft):

!(GWD/STi),;(kw/ft):

(GWD/ST),,(kw/ft)

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.

0 li

TVANuclear Fuel Core Operating LimitsR~rt t

TVA-COLR-BF2Ci0 Revision 4, Page 15 Figure 5 APLHGR Limits for Bundle Type GE9B-PSDWB325-10GZ (GE8X8NB) 15 14 13.

12 TABLEOPERATIO NACCEP 10 9.

8 E

cc 7

X 6

5 CCEPTABLE OPERATIO 0

0 10.0 20.0 30.0 Cyclo Exposure (GWD/ST) 40.0 50.0 verage~

anar'"

Exposu're.

'Limit (GWD/ST)...(kw/ft).

Most Limiting Lattice for Each Exposure Point

verage, anar '

i Exposure Limit

(GWDIST)

.:.",,(kw/ft) verage~, anar Exposure Limit (GWD/ST)

(kw/ft),

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.

TVANuclear Fuel Core Operating Limits R~crt t

TVA-COLR-BF2C10 Revision 4, Page 16 Figure 6 APLHGR Limits for Bundle Type GE9B-PSDWB326-7GZ (GE8XSNB) 15 14, 13.

NACCE TIO PTABLE OPERA 12 10 9

8.

cc 7

to 6

5 CCEPTABLE OPERATIO 0

0.0 10.0 20.0 30.0 Cyclo Exposuro (GWD/STj 40.0 50.0 verage,,

anar

Exposur'e

'L'imlt.

-, i(GWD/STi)i.,

'(kw/ft)',.

'ost Umiting Lattice for Each Exposure Point

. - verage

. anar:,

i veragei anar-

'Exposure

'L'lmlt

=

Expo'sure'Llmlt i(GWD/ST),

.(kwlft)': I,,(GWD/STi)

(kwlft)

These values apply to both Turbine Bypass In4ervice and Out-Of4ervlce.

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.

0 0

TVANuclear Fuel Core Operating LimitsR~rt t

TVA-COLR-BF2CI0 Revision 4, Page 17 I

\\

Figure 7 APLHGR Limits for Bundle Type BPSDRB301L (BP8XSR) 15 14 13 12 ERATIO NACCEPTABLE OP 10 8.

E 7-U 6

5.

CCEPTABLE OPERATIO 0

0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 cyclo Exposure (GwD/ST) veraget, anar

Exposure Limit

';-'!(GWD/STi)

",,(kw/ft) verage.

anar:.

Exposure,.

'Limit'(GWD/ST)

".""'!(kw/ft)'erage, anar

~Exposure Limit (GWD/STi) '(kw/ft)

These values apply to both Turbine Bypass In<ervice and Out-Of-Sewlce.

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.

Cl

TVANuclear Fuel Core Operating Limits R~rt t

TVA-COLR-BF2CI0 Revision 4, Page 18 Figure 8 APLHGR Limits for Bundle Type BPSDRB299 (BP8X8R) 15 14 13

~

12 NACCEPTABLE OPERATIO 10 9

8 E

lY 7

to 6

5.

CCEPTABLE OPERATIO 0

0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 Cyclo Exposuro (GWD/ST) veragei anar "Exposure IL'imlt I

'(GWD/STi),

(kw/ft),

yeragei,anar

'Exposure

,.:(GWD/ST):

verage~

anar

'Limit

'Exposure Limit (kw/ft):,:;,

(GWD/ST)

(kwlft)

These values apply to both Turbine Bypass InServlce and Out-OfService.

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.

ik 0

TVANuclear Fuel Core Operating Limits R~eort t

TVA-COLR-BF2C10 Revision 4, Page 19 Figure 9 Power Dependent MAPLHGRFactor - MAPFAC(P) 1.2

'0.8

<<50% Core Flow O<

0.6 I

0.4 0.2

> 50% Core 10 20 I

Flow I

I I

I 30 40 50 60 Power (% Rated) 70 80 90 100 MAPLHGR(P) = MAPFAC(P) x MAPLHGRstd MAPLHGRstd = Standard MAPLHGRLimits For 30% (P For 25% )P:

NO THERMALLIMITSMONITORINGREQUIRED For 25%

<<' ( 30%: MAPFAC(P) = 0.60+ 0.005(PQ0%)

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 In-Service and Out-Of-Service

0 41

TVANuclear Fuel Core Operating Limits l%$5rt TVA-COLR-BF2CI0 Revision 4, Page 20 Figure 10 Flow Dependent MAPLHGRFactor - MAPFAC(F)

MAXFLOW > 102.5'h 0.9 0.8.

cY 0.7 MAXFLOW>tOP/

0.6 0.5 0.4 30 40 60 70 Coro Flow (% Ratod) 80 MAPLHGR(F) = MAPFAC(F) x MAPLHGRstd MAPLHGRstd = Standard MAPLHGR Limits MAPFAC(F) = MINIMUM(1.0, Af*Wc /100 + Bf)

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

axmum l

I ~Core.F,low, I(%'ated) 102.5 107.0 Af 0.6784 0.6758 0.4861 0.4574 These values bound both Turbine Bypass In-Service and Out-Of-Service.

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).

TVANuclear Fuel Core Operating Limits R~rt t

TVA-COLR-BF2CI0 Revision 4, Page 21 Figure 11 MCPR Operating Limitfor GE13 1.46 1.45 1.44.

o 1.43 a.

1.42 1.41.

1.4 E

1.39 Ve 1.38 1.37

~o1 36 1.35 1.34

~ ~

ur no ypass an oc rcu at on urnp r p n orv co 1.33 0

0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1

ptton 8 Option A Tau (x)

':: xposure~

ange;",

to 0

to u;

erytce na ur ine ypass ecircu a ton ump np p ton.,

p ton',

Tau=1 0 Tau=.0.'0 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.

0 0

TVANuclear Fuel Core Operating Limits R~rt t

TVA-COLR-BF2C10 Revision 4, Page 22 Figure 12 MCPR Operating Limitfor GE11 1.44 1.43.

1.42

~ r K 1.41 O

1.4 0

1.39 E

1.38 C

137 0

1.36 D

1.35-1.34 ur mo ypassan ocrcua on ump rp n orvco 1.33 0

0.1 Option 8 0.2 0.3 0.4 0.5 0.6 0.7 0.8 Tau

(~)

0.9 Option A posurei ange-i u

- ervce na

p on'"

', '. 'Tau=1';0 p on Tau=.0.0 0

ur ine ypass 0

earcu a ion ump np 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.

II

TVANuclear Fuel Core Operating Limits rt t

TVA-COLR-BF2C10 Revision 4, Page 23 Figure 13 MCPR Operating Limitfor GE9B (GESXSNB) 1.4 1.39, C) 1.38 K

1.37 O

E 136.

g 1.35

~

Q0 O

1.33 ur ino ypass an octrcua on ump rp n orv co r

r r

1.32 0

Option B 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Option A Tau (v) posure:

ange;,.

El 0

0 0

u

- erytce'---

na u

tne ypass ectrcu a ton ump np p ton; Tau=i.'0 p

on~

Tau=0.0 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.

Cl I

TVANuclear Fuel'ore Operating Limits R rt t

TVA-COLR-BF2C10 Revision 4, Page 24 Figure 14 MCPR Operating Limitfor GE7B (BP8X8R) 1.39 CI CI 1.38 1.37.

D

~

1.36.

E g 1.35.

O 1.34 O

1.33, ur no ypass an ec rcu a on ump p n orv co 1.32 0

Option 8 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Tau

(~)

1 Option A

! xposure!

ange; I

I 0

0 u

erv ce na u

ine ypass ectrcu a ton ump np p on i

!'plonI Tau=.1!0 Tau=,0.'0 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.

0

, ~

4

TVANuclear Fuel Core Operating Limits Report TVA-COLR-BF2C10 Revision 4, Page 25, Figure 15 Power Dependent MCPR(P) Limits 3.2

+50)t FLOWr(BOOS) 2.8 0-to 2.6 4

m 2.4 0 o 2.2 t6 V Y L 1.8 1.6.

1.4

>505'LOW (Equipment l~

6 RPTOOS) 350)5 FLOW (Eqttpment nservt ce 6 RPTOOS)

(MOOS) 1.2 10 I

I 20 30 40 50 60 Powor (% Ratod) 70 80 90 100 OPERATING LIMITMCPR(P) = Kp '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 and RPT In-Service or RPT Out-Of-Service RPTOOS Kbyp =1.97 For < 50% CORE FLOW Kbyp=2.21 For > 50% CORE FLOW Turbine B ass Out-Of clervlce TBOOS Kbyp=2.01 For <<50% CORE FLOW Kbyp = 3.01 For >

50% CORE FLOW Fol'0% < 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.

4 Ik

TVANuclear Fuel P

Core Operating LimitsR~rt TVA-COLR-BF2C10 Revision 4, Page 26 (Final)

Figure 16 Flow Dependent MCPR Operating Limit-MCPR(F) 1.7 1.6 1.5 1.4 MAXFLOW~ 107%

1.3 MAXFLOW~ tCL5%

1.2 30 40 50 60 70 Coro Flow (% Rated) 60 90 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:

ax mum,,;:

.Core;Flow'-,.Af '.'"

(%'Rated);;'i

'rBf I

102.5 107.0 4).587 4).603 1.701 1.745 These values bound both Turbine Bypass In4ervice and Out-Of<ervlce.

These values bound both Recirculation Pump Trip Inervice and Out&f<ervice Either Turbine Bypass or Recirculation Pump Trip may be Out-OfZervice.

The core is not analyzed for a combination of TBOOS and RPTOOS.

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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