ML18039A482
| ML18039A482 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/09/1998 |
| From: | Bruce A, Keys T, Riley E TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18039A481 | List: |
| References | |
| NUDOCS 9808210172 | |
| Download: ML18039A482 (44) | |
Text
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, 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: p/r/8P Earl E. Riley, Engineering Specialist BWR Fuel Engineering Verified By: Date: 4 > gP Alan L. Bruce, Nuclear Engineer BWR Fuel Engineering Approved By:
T. A. Keys, Man er BWR Fuel Engin ering Reviewed By:
e ctor Engineering Supervisor Reviewed By:
Revision 2 (7/8/98)
'it8082LOi72 9808i7 ADOCK 05000260 Q(
g PDR Revise for Improved Technical Specification Implementation Pages Affected: All
N
,/
- l j
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 2 Revision Log Revision Date ~Desert tion Affected Pa es 0 9/25/97 Initial Release All 5/21/98 Revise Tau Calculation (ref. BFN PER I, 2, 6, 9 no. 98-005651-000) 7/8/98 Revise to Implement Improved Technical All Specification Requirements
I TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, 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 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 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 Specification Table 3.3.2.1-1)
- f. Shutdown Margin (SDM) Limit (Technical Specification 3.1.1)
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 4
- 2. APLHGR LIMIT(TECHNICAL SPECIFICATIONS 3.2.1 AND 3.7.5)
The APLHGR limits for full power and flow conditions for each type of fuel as a function of exposure are shown in Figures 1-8. The APLHGR limits for the GE9B, GE11 and GE13 assemblies are for the most limiting lattice (excluding natural uranium) at each exposure point. The specific values for each lattice are given in Reference 4.
These APLHGR limits are adjusted for off-rated power and flow conditions using the ARTS factors, MAPFAC(P) and MAPFAC(F). The reduced power factor, MAPFAC(P),
is given in Figure 9. Similarly, adjustments for reduced flow operation are performed using the MAPFAC(F) corrections given in Figure 10. Both factors are multipliers used to reduce the standard APLHGR limit. The most limiting power-adjusted or flow-adjusted value is taken as the APLHGR operating limit for the off-rated condition.
The APLHGR 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.
7 TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision2, Page5
- 3. LHGR LIMIT(TECHNICAL SPECIFICATION 3.2.3)
The LHGR limit for unit 2 cycle 10 is fuel type dependent, as shown below:
Fuel Type LHGR Limit GE7B (BP8X8R) 13.4 kw/ft GE9B (GE8X8NB) 14.4 kw/ft GE11 14.4 kw/ft GE13 14.4 kw/ft
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 6
- 4. OLMCPR (TECHNICAL SPECIFICATIONS 3.2.2, 3.3.4.1, AND 3.7.5)
is equal to the fuel type and exposure dependent limit shown in Figures 11 thru 14.
The actual OLMCPR(100) value is dependent upon the scram time testing results, as described below:
Cave CB
'C = 0.0 or whichever is greater where; 'C= 1.096 sec (analytical Option A scram time limit - based on dropout time for notch position 36) n i=1 ave n
t N 2 p+165~a~ n where; p = 0.830 sec (mean scram time used in transient analysis-based on dropout time for notch position 36) a = 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
~; = Scram time (dropout time) from fully withdrawn 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 15 and 16, respectively. The most limiting power-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. These events are analyzed separately and the core is not analyzed for both systems Out-Of-Service at the same time.
4
TVANuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 7
- 5. APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL REQUIREMENTS MANUALSECTION 5.3.1 AND TABLE 3.3.4-1)
The APRM Rod Block trip setting shall be:
SRB < (0.66W + 66%) Allowable Value SRB < (0.66W+ 64%) Nominal Trip Setpoint (NTSP) where:
SRB = Rod Block setting in percent of rated thermal power (3293 MWt)
W = Loop recirculation flow rate in percent of rated The APRM Rod Block trip setting is clamped at a maximum allowable value of 115%
(corresponding to a NTSP of 113%).
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 8
- 6. ROD BLOCK MONITOR (RBM) TRIP SETPOINTS AND OPERABILITY (TECHNICAL SPECIFICATION TABLE 3.3.2.1-1)
The RBM trip setpoints and applicable power ranges shall be as follows:
RBM Trip Setpoint Allowable Value Nominal Trip Setpoint (AV) (NTSP LPSP 27% 25%
IPSP 62% 60%
HPSP 82% 80%
LTSP - unfiltered 121.7% 120.0%
- filtered 120.7% 119.0% (l) (2)
ITSP - unfiltered 116.7% 115.0%
- filtered 115.7% 114.0% (>) (2)
HTSP - unfiltered 111.7% 110.0%
- filtered 110.9% 109.2% (l) (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).
The RBM setpoints in Technical Specification Table 3.3.2.1-1 are applicable when:
THERMALPOWER Applicable Notes from
'CPR Table 3.3.2.1-1
> 27% and < 90% RATED < 1.75 (a) (b) (f) (h)
) 90% RATED < 1.44 (g)
Note: The given MCPR operating limits are adjusted to correspond to a MCPR safety limit of 1.10. The values shown correspond to operating limits of 1.70 and 1.40 given the original 1.07 MCPR safety limit used in reference 6.
I f
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 9
- 7. SHUTDOWN MARGIN (SDM) LIMIT (TECHNICAL SPECIFICATION 3.1.1)
The core shall be subcritical with the following margin with the strongest OPERABLE control rod fully withdrawn and all other OPERABLE control rods fully inserted.
SDM ) 0.38% dk/k
I TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, 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 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] 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 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]
I f
TVA Nuclear Fuel TVA-COLR-BF2C1 0
~
Core Operating Limits Report Revision 2, Page 11 Figure 1 APLHGR Limits for Bundle Type GE13-P9HTB384-1264.0 (GE13) 15 14.
13.
- 12. NACCEPTABLE OP ERATIO 10 8.
E 3 CCEPTA BLE OPERATIO 7.
(s 6.
5, 4,
0.
0 10.0 20.0 30.0 40.0 50.0 Cycie Exposure (GWD/ST)
Most Limiting Lattice for Each Exposure Point ve rage anar; yerage anar, verage anar Exposure, Limit=':-' Exposure . Limit, Exposure Limit (GWD/ST) 'kw/ft),, (GWD/ST),, (kw/ft) (GWD/ST) (kw/ft),
These values apply to both Turbine Bypass In4ervice and Out-ofNervlce.
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 12 Figure 2 APLHGR Limits for Bundle Type GE11-P9HUB366-12G4.0 (GE11) 15 14.
13.
12 MACCEPTABLE OP ERATIO 10.
8 E
7 CCEPTA BLE OPERATIO Cs 6
5 0
0.0 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWD/ST)
Most Limiting Lattice for Each Exposure Point verage anar -
verage, anar, verage anar Exp'osure 'imit Exposure -
Limit ... Exposure - Limit
..:,, (kw/ft)...,,,
=
(GWD/ST) (GWD/ST),,-,, (kw/ft) (GWD/ST).i, .
(kw/ft)
These values apply to both Turbine Bypass In4ervice and Out-Of4ervice.
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 13 1
Figure 3 APLHGR Limits for Bundle Type GE11-P9HUB367-14GZ (GE11) 15 14, 13.
12 NACCEPTABLE OPERATIO 10 ~
8, E
3 CCEPTA BLE OPERATIO 7
Co 5
5.
0.
0.0 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWD/ST)
Most Limiting Lattice for Each Exposure Point verage anar verage anar verage anar Exposure 'imit 'xposure Limit Exposure Limit (GWD/ST) (kw/ft),, (GWD/ST).,, (kwlft) (GWD/ST) (kwlft)
These values apply to both Turbine Bypass Inervice and Out-Of-Service.
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 14 Figure 4 APLHGR Limits for Bundle Type GE9B-PSDWB319-9GZ (GE8X8NB) 15 14.
13,
- 12. NACCEP TABLE OPERAT IO 10.
8.
E CCEPTABLE OPERATIO IY 7 ~
co X
6.
5.
0.
0 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWD/ST)
Most Limiting Lattice for Each Exposure Point verage an ar verage anar verage anar-
'xposure Limit, Exposure Limit Exposure . Limit
'GWD/ST) -
'(kw/ft) (GWD/ST) (kwlft) (GWD/ST) (kw/ff)
These values apply to both Turbine Bypass In4ervice and Out-OfZervice.
TVA Nuclear Fuel TVA-COLR-BF2C10
~
Core Operating Limits Report Revision 2, Page 15 1
Figure 5 APLHGR Limits for Bundle Type GE9B-P8DWB325-10GZ (GE8X8NB) 15, 14.
13-
- 12. NACCEPTABLE OPERATIO 10-8-
E 3 CCEPTABLE OPERATIO cc 7 cs K
6.
5 ~
0 0 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWDIST) verage anar
'ost Limiting Lattice for Each Exposure Point verage anar verage anar Exposure =
='
Limit Exposure Limit Exposure Limit (GWD/ST)' 'kw/ft) (GWD/ST) (kw'Ift) (GWD/ST)'kw/ft)
These values apply to both Turbine Bypass In4ervice and Out-Of4ervice.
TVA Nuclear Fuel TVA-COLR-BF2CIO Core Operating Limits Report Revision 2, Page 16 I
Figure 6 APLHGR Limits for Bundle Type GE9B-P8DWB326-7GZ (GE8X8NB) 15 14.
13 NACCE PTABLE OPE RATIO 12 10.
8.
E
- 7. CCEPTABLE OPERATIO ts 6.
5.
0 0.0 10.0 20.0 30.0 40.0 50.0 Cycle Exposure (GWD/ST)
Most Limiting Lattice for Each Exposure Point verage anar Exposure (GWD/ST)
'imit
='kw/ft) yerage, anar, Exposure
'GWD/ST)
Limit (kwlft) verage,, anar.
Exposure (GWD/ST)
Limit, (kwlft) 0 These values apply to both Turbine Bypass In4ervice and Out-Of4ervice.
~ ~
I
TVA Nuclear Fuel TVA-COLR-BF2C10
~
Core Operating Limits Report Revision 2, Page 17 1
Figure 7 APLHGR Limits for Bundle Type BPSDRB301L (BP8X8R) 15 14.
NACCEPTABLE OP E RATIO 13.
12 10.
- 8. CCEPT ABLE OP ERATIO E
7 ~
Cs 6.
5 0
0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 Cycle Exposure (GWD/ST) verage anar- "
verage anar verage anar
. Exposure Limit -:Exposure i,. Limit Exposure 'imit
, (GWD/ST) (kwlft) (GWD/ST) (kwlft) (GWD/ST) (kwlft)
These values apply to both Turbine Bypass In4ervice and Out-Of4ervice.
C TVA Nuclear Fuel TVA-COLR-BF2CI 0
~
Core Operating Limits Report Revision 2, Page 18 Figure S APLHGR Limits for Bundle Type BPSDRB299 (BP8X8R) 15 14.
NACCEPTABLE OPERATIO 13-12.
10, 8,
E CCEPTA BLE OPERA TIO 7 ~
ts 6.
5 ~
0 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 Cycle Exposure (GWD/ST) verage anar verage anar yerage, anar
'xposure Limit Exposure Limit Exposure, Limit (GWD/ST) (kwlft), (GWDIST),, (kwlft), , (GWD/ST) (kw/ft)
These values apply to both Turbine Bypass In4ervlce and Out-Of4ervlce.
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 19 Figure 9 Power Dependent MAPLHGR Factor - MAPFAC(P) 1.2 0.8 . < 50% Core Flow O
+ 0.6 .
0,4, I
> 50% Core Flow 0.2 .
I I
I 0.
10 20 30 40 50 60 70 80 90 100 Power (% Rated)
MAPLHGR(P) = MAPFAC(P) x MAPLHGRstd For 25% >
Fol 25%
P:
MAPLHGRstd = Standard MAPLHGR Limits NO THERMAL LIMITS MONITORING REQUIRED
( P ( 30%: MAPFAC(P) = 0.60+ 0.005(P-30%) For < 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
I' g ~
0
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 20 Figure 10 Flow Dependent MAPLHGR Factor - MAPFAC(F)
MAX FLOW > 102.5%
0.9 .
0.8 .
O 0.7 .
~ 107%
0.6 .
0.5 .
0.4 30 40 50 60 70 80 90 Coro Flow (% Ratod)
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 Bf are Constants Given Below:
ax mum
'Core Flow
(% Rated)
'f
Bf.
102.5 0.4861
'.6784 107.0 0.6758 0.4574 These values bound both Turbine Bypass In-Service and Out-Of-Service.
The 102.5% maximum flow line Is used for operation up to 100% rated flow.
The 10?% maximum flow line is used for operation up to 105% rated flow (ICF).
TVA Nuclear Fuel TVA-COLR-BF2CI 0
~
Core Operating Limits Report Revision 2, Page 21 Figure 11 MCPR Operating Limit for GE13 1.46 1.45, 1.44 .
~ ~
1.43 .
- o. 1.42 ~
O
~ r 1.41 .
1.4 BOSS E ~ ~
~ ~
1.39 1.38,
~ r 1.37 .
o" o 136 1.35, ur ne ypass an oc rcu at on ump rp n orvco 1.34 1.33 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Option B Option A Tau (~)
xposure ange u- - ervce p ton p ion Tau=1.0 Tau=0.0 0 na ur ine ypass 0 ecircu 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.
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 22 Figure 12 MCPR Operating Limit for GE11 1.44 1.43 1.42 1.41 . PTOO O
1.4 .
1.39 .
E a) 138.
I-I CL 137.
0 1.36 .
O ~ ~
> 1.35, ur no ypass an oc rcu at on ump r p n orv co 1.34 .
1.33 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 Option 8 Option A Tau (x) xposure ange =. u- - ervce p ton p lon Tau=1.0 ,. Tau=0.0.
0 na ur ine ypass 0 ectrcua ion ump rtp 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.
~ ~
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 23 Figure 13 MCPR Operating Limit for GE9B (GESXSNB) 1.4, 1.39 ~
CI 1.38 .
Yr O
1.37 ~
0I E 1.36. BOOS P. 1.35 .
K 0
~ 134.
O ur ne ypass an ec rc ua on um p rpn erv co 1.33 .
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 (~)
xposure: ange u- - ervce p on p on
-, Tau=1.'0 'Tau=0.0 na ur ine ypass eclrcu 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.
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 24 Figure 14 MCPR Operating Limit for GE7B (BPSXSR) 1.39 1.38 .
CI 1.37 .
O PT60 X
~ 1.36 E
g 1.35.
CL O 1.34 O ur no ypass an oc rcua on u mp rp n 1.33 1.32 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Option 8 Option A Tau (x) xposure ange. u- - ervce p lon p ton
- Tau=,1.0 Tau=0.0 na ur tne ypass ectrcu a ton 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.
~ ~
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 25
\
Figure 15 Power Dependent MCPR(P) Limits 3.2
>50sa FLow tTBoos)
- g. 2.8
~4 aL aa as aa 2.6 .
A aL 2.4.
0 bC S4 c>
Q O.
22 >50)a FLow (EqaapslaAa Ih Bats)as
~ FLOW tTBOOS) a RpToos)
<<s pg 2
<<50'k FLOW gf 18 taqaapmsnt a a RpToos)
>Ssaaaas 1.6 O 0 1.4 .
I2 1.2 0 10 20 30 40 50 60 70 80 90 100 Powor (% Ratodi OPERATING LIMITMCPR(P) = Kp
- OLMCPR(100)
For P <25% NO THERMAL LIMITS MONITORING 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-Service TBOOS Kbyp = 2.01 For < 50% CORE FLOW Kbyp = 3.01 For > 50% CORE FLOW For 30% < P<45% : Kp = 1.28 + 0.01340(45%-P)
For 45% < P <60% Kp = 1.15+ 0.00867(60%-P)
For 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 RPT6OS at the same time.
~ ~
TVA Nuclear Fuel TVA-COLR-BF2C10 Core Operating Limits Report Revision 2, Page 26 (Final)
Figure 16 Flow Dependent MCPR Operating Limit - MCPR(F) 1.7 1.6 1.5 .
1.4 .
MAXFLOW < 107%
I MAXFLOW 102.5%
1.3 30 40 50 60 70 80 90 100 Core F tow (% Rated)
For Wc < 40% : MCPR(F) = (Af'Wc/100+ Bf)*[1+0.0032(40-Wc)]
For Wc > 40% : MCPR(F) = MAX(1.23, Af"Wc/100+ Bf)
Wc =% Rated Core Flow Af and Bf are Constants Given Below:
ax mum Core Flow
'(% Rated) Bf'.701 102.5 %.587 107.0 -0.603 1.745 These values bound both Turbine Bypass In4ervice and Out-Of4ervice.
These values bound both Recirculation Pump Trip InZervice and Out-Of4ervice Either Turbine Bypass or Recirculation Pump Trip may be Out-Ofervice.
The core is not analyzed for a combination of TBOOS and RPTOOS.
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).
ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 3 CORE OPERATING LIMITS REPORT (COLR) I REVIS ION 3 FOR CYCLE 8 OPERATION (SEE ATTACHED)