NRC-22-0006, Transmittal of the Core Operating Limits Report for Cycle 22
| ML22067A091 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 03/08/2022 |
| From: | Bennett E DTE Electric Company |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC-22-0006 | |
| Download: ML22067A091 (32) | |
Text
DTE Electric Company 6400 N. Dixie Highway Newport, MI 48166 March 8, 2021 TS 5.6.5 NRC-22-0006 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Fermi 2 Power Plant NRC Docket No. 50-341 NRC License No. NPF-43
Subject:
Transmittal of the Core Operating Limits Report for Cycle 22 In accordance with Fermi 2 Technical Specification 5.6.5, DTE Electric Company (DTE) hereby submits a copy of the Core Operating Limits Report (COLR) for Cycle 22. This COLR will be used during the Fermi 2 twenty-second operating cycle.
No new commitments are being made in this submittal.
Should you have any questions or require additional information, please contact me at (734) 586-4273.
Sincerely, Margaret M. Offerle for Ertman L. Bennett III Manager - Nuclear Licensing
Enclosure:
Core Operating Limits Report (COLR), Cycle 22 cc: NRC Project Manager NRC Resident Office Regional Administrator, Region III
Enclosure to NRC-22-0006 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 Core Operating Limits Report (COLR), Cycle 22
COLR - 22 Revision 0 Page 1 of30 FERMI2 CORE OPERATING LIMITS REPORT CYCLE 22 REVISION0 Prepared by: 1/13/2022 PaulR. Kiel Date Principal Technical Expert, Reactor Engineering Reviewed by: 1/14/2022 Jeremy J. McGrew Date Principal Engineer, Reactor Engineering Approved by:
Michael A. Lake Supervisor, Reactor Engineering March 2022
COLR - 22 Revision 0 Page 2 of 30 TABLE OF CONTENTS
1.0 INTRODUCTION
AND
SUMMARY
.................................................................................... 4 2.0 SAFETY LIMIT MINIMUM CRITICAL POWER RATIO .................................................. 5 2.1 Definition ........................................................................................................................ 5 2.2 Determination of Cycle Specific SLMCPR .................................................................... 5 3.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE............................................ 6 3.1 Definition ........................................................................................................................ 6 3.2 Determination of MAPLHGR Limit ............................................................................... 6 3.2.1 Calculation of MAPFAC(P) ..................................................................................... 9 3.2.2 Calculation of MAPFAC(F) ................................................................................... 11 4.0 MINIMUM CRITICAL POWER RATIO............................................................................. 12 4.1 Definition ...................................................................................................................... 12 4.2 Determination of Operating Limit MCPR .................................................................... 12 4.3 Calculation of MCPR(P) ............................................................................................... 14 4.3.1 Calculation of KP .................................................................................................... 14 4.3.2 Calculation of ....................................................................................................... 17 4.4 Calculation of MCPR(F) ................................................................................................ 18 5.0 LINEAR HEAT GENERATION RATE ............................................................................... 19 5.1 Definition ...................................................................................................................... 19 5.2 Determination of LHGR Limit...................................................................................... 19 5.2.1 Calculation of LHGRFAC(P) ................................................................................. 22 5.2.2 Calculation of LHGRFAC(F) ................................................................................. 24 6.0 CONTROL ROD BLOCK INSTRUMENTATION ............................................................. 25 6.1 Definition ...................................................................................................................... 25 7.0 BACKUP STABILITY PROTECTION REGIONS ............................................................. 26 7.1 Definition ...................................................................................................................... 26
8.0 REFERENCES
...................................................................................................................... 29
COLR - 22 Revision 0 Page 3 of 30 LIST OF TABLES TABLE 1 FUEL TYPE-DEPENDENT STANDARD MAPLHGR LIMITS ............................ 7 TABLE 2 FLOW-DEPENDENT MAPLHGR LIMIT COEFFICIENTS ................................ 11 TABLE 3 OLMCPR 100/105 AS A FUNCTION OF EXPOSURE AND ................................ 13 TABLE 4 FLOW-DEPENDENT MCPR LIMIT COEFFICIENTS ........................................ 18 TABLE 5 STANDARD LHGR LIMITS FOR VARIOUS FUEL TYPES.............................. 20 TABLE 6 FLOW-DEPENDENT LHGR LIMIT COEFFICIENTS......................................... 24 TABLE 7 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS WITH FILTER 25 LIST OF FIGURES FIGURE 1 BSP REGIONS (NOMINAL FEEDWATER TEMPERATURE)......................... 27 FIGURE 2 BSP REGIONS (FEEDWATER TEMPERATURE REDUCTION)..................... 28
COLR - 22 Revision 0 Page 4 of 30
1.0 INTRODUCTION
AND
SUMMARY
This report provides the cycle specific plant operating limits, which are listed below, for Fermi 2, Cycle 22, as required by Technical Specification 5.6.5. The analytical methods used to determine these core operating limits are those previously reviewed and approved by the Nuclear Regulatory Commission in GESTAR II (Reference 7).
The cycle specific limits contained within this report are valid for the full range of the licensed operating domain.
OPERATING LIMIT TECHNICAL SPECIFICATION SLMCPR95/95 2.1.1.2 APLHGR 3.2.1 MCPR 3.2.2 LHGR 3.2.3 RBM 3.3.2.1 BSP REGIONS 3.3.1.1 SLMCPR = SAFETY LIMIT MINIMUM CRITICAL POWER RATIO APLHGR = AVERAGE PLANAR LINEAR HEAT GENERATION RATE MCPR = MINIMUM CRITICAL POWER RATIO LHGR = LINEAR HEAT GENERATION RATE RBM = ROD BLOCK MONITOR BSP = BACKUP STABILITY PROTECTION
COLR - 22 Revision 0 Page 5 of 30 2.0 SAFETY LIMIT MINIMUM CRITICAL POWER RATIO 2.1 Definition TECH SPEC IDENT OPERATING LIMIT 2.1.1.2 SLMCPR95/95 The Technical Specification SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (SLMCPR95/95) shall be the smallest critical power ratio that exists in the core for each fuel product.
The Technical Specification Safety Limit value is dependent on the fuel product line and the corresponding MCPR correlation, which is cycle independent. The value is based on the Critical Power Ratio data statistics and a 95% probability with 95% confidence that rods are not susceptible to boiling transition. (Reference 14)
The Cycle Specific SLMCPR99.9 presented here is that power in the bundle that is statistically calculated by application of the appropriate correlations and uncertainties to cause some point in the bundle to experience boiling transition, divided by the actual bundle operating power.
2.2 Determination of Cycle Specific SLMCPR The Cycle Specific SLMCPR, which is also known as SLMCPR99.9, is cycle dependent and ensures 99.9% of the fuel rods in the core are not susceptible to boiling transition. (Reference 14) The Operating Limit MCPR is set by adding the SLMCPR99.9 and the change in MCPR for the most limiting anticipated operational occurrence such that fuel cladding will not sustain damage because of normal operation and anticipated operational occurrences.
The SLMCPR99.9 is set such that no significant fuel damage is calculated to occur if the limit is not violated. Since the parameters that result in fuel damage are not directly observable during reactor operation, the thermal and hydraulic conditions that result in the onset of transition boiling are used to mark the beginning of the region in which fuel damage could occur. Although the onset of transition boiling would not result in damage to BWR fuel rods, the critical power at which boiling transition is calculated to occur has been adopted as a convenient limit.
For this cycle, the Two Loop and Single Loop SLMCPR99.9 values (Reference 2) are:
Two Loop SLMCPR = 1.08 Single Loop SLMCPR = 1.11
COLR - 22 Revision 0 Page 6 of 30 3.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 3.1 Definition TECH SPEC IDENT OPERATING LIMIT 3.2.1 APLHGR The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) shall be applicable to a specific planar height and is equal to the sum of the LINEAR HEAT GENERATION RATEs (LHGRs) for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the bundle at the height.
3.2 Determination of MAPLHGR Limit The maximum APLHGR (MAPLHGR) limit is a function of reactor power, core flow, fuel type, and average planar exposure. The limit is developed, using NRC approved methodology described in References 7 and 8, to ensure gross cladding failure will not occur following a loss of coolant accident (LOCA). The MAPLHGR limit ensures that the peak clad temperature during a LOCA will not exceed the limits as specified in 10CFR50.46(b)(1) and that the fuel design analysis criteria defined in References 7 and 8 will be met.
The MAPLHGR limit during dual loop operation is calculated by the following equation:
MAPLHGRLIMIT = MIN (MAPLHGR (P), MAPLHGR (F))
where:
MAPLHGR (P) = MAPFAC (P) x MAPLHGRSTD MAPLHGR (F) = MAPFAC (F) x MAPLHGRSTD Within four hours after entering single loop operation, the MAPLHGR limit is calculated by the following equation:
MAPLHGRLIMIT = MIN (MAPLHGR (P), MAPLHGR (F))
where:
MAPLHGR (P) = MAPFAC (P) x MAPLHGRSTD MAPLHGR (F) = MAPFAC (F) x MAPLHGRSTD MAPFAC (P) and MAPFAC (F) are limited to 0.90 The Single Loop Operation multiplier on MAPLHGR is 0.90. (Reference 2)
COLR - 22 Revision 0 Page 7 of 30 MAPLHGRSTD, the standard MAPLHGR limit, is defined at a power of 3486 MWth and flow of 105 Mlbs/hr for each fuel type as a function of average planar exposure and is presented in Table
- 1. (Reference 2) When hand calculations are required, MAPLHGRSTD shall be determined by interpolation from Table 1. MAPFAC(P), the core power-dependent MAPLHGR limit adjustment factor, shall be calculated by using Section 3.2.1. MAPFAC(F), the core flow-dependent MAPLHGR limit adjustment factor, shall be calculated by using Section 3.2.2.
TABLE 1 FUEL TYPE-DEPENDENT STANDARD MAPLHGR LIMITS GE14 Exposure GE14 MAPLHGR GWD/ST kW/ft 0.0 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 Fuel Types GE14-P10CNAB385-13GZ-100T-150-T6-4571 GE14-P10CNAB384-15GZ-100T-150-T6-4572 GE14-P10CNAB383-13GZ-100T-150-T6-4573 GE14-P10CNAB377-15GZ-100T-150-T6-4574 GE14-P10CNAB383-8G6.0/5G5.0-100T-150-T6-4478 GE14-P10CNAB383-8G6.0/7G5.0-100T-150-T6-4479 GE14-P10CNAB383-2G6.0/11G5.0-100T-150-T6-4480 GE14-P10CNAB383-10G6.0/5G5.0-100T-150-T6-4481
COLR - 22 Revision 0 Page 8 of 30 TABLE 1 (Continued)
FUEL TYPE-DEPENDENT STANDARD MAPLHGR LIMITS GNF3 Exposure GNF3 MAPLHGR GWD/ST kW/ft 0.0 14.36 9.07 13.78 21.22 13.01 40.82 10.75 57.60 8.00 63.50 6.00 Fuel Types GNF3-P10CG3B388-14GZ-83AV-150-T6-4661 GNF3-P10CG3B399-14GZ-83AV-150-T6-4662 GNF3-P10CG3B402-16GZ-83AV-150-T6-4663 GNF3-P10CG3B419-16GZ-83AV-150-T6-4664 GNF3-P10CG3B403-16GZ-83AV-150-T6-4888 GNF3-P10CG3B403-15GZ-83AV-150-T6-4889 GNF3-P10CG3B421-13GZ-83AV-150-T6-4890 GNF3-P10CG3B420-13GZ-83AV-150-T6-4891 GNF3-P10CG3B404-16GZ-83AV-150-T6-4892 GNF3-P10CG3B404-14GZ-83AV-150-T6-4893
COLR - 22 Revision 0 Page 9 of 30 3.2.1 Calculation of MAPFAC(P)
The core power-dependent MAPLHGR limit adjustment factor, MAPFAC(P) (Reference 2, 3 &
10), shall be calculated by one of the following equations.
For 0 P < 25 :
No thermal limits monitoring is required.
For 25 P 29.5 :
With All Equipment OPERABLE, or MSR INOPERABLE For core flow < 50 Mlbs/hr, MAPFAC (P) = 0.568 + 0.00156 (P - 29.5)
For core flow 50 Mlbs/hr, MAPFAC (P) = 0.568 + 0.00156 (P - 29.5)
With Turbine Bypass INOPERABLE, or Turbine Bypass and MSR INOPERABLE For core flow < 50 Mlbs/hr, MAPFAC (P) = 0.488 + 0.01067 (P - 29.5)
For core flow 50 Mlbs/hr, MAPFAC (P) = 0.436 + 0.00511 (P - 29.5)
For 29.5 < P 45 :
MAPFAC (P) = 0.713 + 0.00529 (P - 45)
For 45 < P 60 :
MAPFAC (P) = 0.791 + 0.00520 (P - 60)
For 60 < P 85 :
MAPFAC (P) = 0.922 + 0.00524 (P - 85)
For 85 < P 100 :
MAPFAC (P) = 1.000 + 0.00520 (P - 100) where: P = Core power (fraction of rated power times 100).
COLR - 22 Revision 0 Page 10 of 30 MAPFAC(P) for Pressure Regulator Out of Service (PROOS) Limits With one Turbine Pressure Regulator Out of Service and Reactor Power Greater Than or Equal to 25% and both Turbine Bypass and Moisture Separator Reheater (MSR) Operable:
For 25 P 29.5 :
For core flow < 50 Mlbs/hr, MAPFAC (P) = 0.568 + 0.00156 (P - 29.5)
For core flow 50 Mlbs/hr, MAPFAC (P) = 0.568 + 0.00156 (P - 29.5)
For 29.5 < P 45 :
MAPFAC (P) = 0.680 + 0.00626 (P - 45)
For 45 < P 60 :
MAPFAC (P) = 0.758 + 0.00520 (P - 60)
For 60 < P 85 :
MAPFAC (P) = 0.831 + 0.00292 (P - 85)
For 85 < P 100 :
MAPFAC (P) = 1.000 + 0.00520 (P - 100) where: P = Core power (fraction of rated power times 100).
Note: Pressure regulator in service and out of service limits are identical for power >85%.
COLR - 22 Revision 0 Page 11 of 30 3.2.2 Calculation of MAPFAC(F)
The core flow-dependent MAPLHGR limit adjustment factor, MAPFAC(F) (Reference 2, 3, &
10), shall be calculated by the following equation:
WT MAPFAC(F)= MIN(C, AF + BF )
100 where:
WT = Core flow (Mlbs/hr).
AF = Given in Table 2.
BF = Given in Table 2.
C = 1.0 in Dual Loop and 0.90 in Single Loop.
TABLE 2 FLOW-DEPENDENT MAPLHGR LIMIT COEFFICIENTS Maximum Core Flow*
(Mlbs/hr) AF BF 110 0.8889 0.2613 As limited by the Recirculation System MG Set mechanical scoop tube stop setting.
COLR - 22 Revision 0 Page 12 of 30 4.0 MINIMUM CRITICAL POWER RATIO TECH SPEC IDENT OPERATING LIMIT 3.2.2 MCPR 4.1 Definition The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest Critical Power Ratio (CPR) that exists in the core for each type of fuel. The CPR is that power in the bundle that is calculated by application of the appropriate correlation(s) to cause some point in the bundle to experience boiling transition, divided by the actual bundle operating power.
4.2 Determination of Operating Limit MCPR The required Operating Limit MCPR (OLMCPR) (Reference 2) at steady-state rated power and flow operating conditions is derived from the established fuel cladding integrity Safety Limit MCPR and an analysis of abnormal operational transients. To ensure that the Safety Limit MCPR is not exceeded during any anticipated abnormal operational transient, the most limiting transients have been analyzed to determine which event will cause the largest reduction in CPR. Three different core average exposure conditions are evaluated. The result is an Operating Limit MCPR which is a function of exposure and . is a measure of scram speed and is defined in Section 4.3.2.
The limiting OLMCPR shall be represented by the following equation:
OLMCPR = MAX(MCPR(P), MCPR(F))
The process to calculate MCPR(P), the core power-dependent MCPR operating limit, is illustrated in Section 4.3.
The process to calculate MCPR(F), the core flow-dependent MCPR operating limit, is illustrated in Section 4.4.
In case of Single Loop Operation, the Safety Limit MCPR is increased to account for increased uncertainties in core flow measurement and TIP measurement. For Single Loop Operation, the OLMCPR is increased by 0.03 (Reference 2) from the Two Loop OLMCPR.
COLR - 22 Revision 0 Page 13 of 30 In case of operation with one Turbine Pressure Regulator out of service, OLMCPR limits are bounding when reactor power is less than 29.5% or greater than 85%. When reactor power is greater than or equal to 29.5% and less than or equal to 85%, then operation with one Turbine Pressure Regulator out of service is permitted if both Turbine Bypass Valves and the Moisture Separator Reheater are operable. (Reference 2 and 3)
TABLE 3 OLMCPR 100/105 AS A FUNCTION OF EXPOSURE AND EXPOSURE CONDITION (MWD/ST) OLMCPR100/105 BOTH Turbine Bypass Valves AND Moisture Separator Reheater Two Loop Single Loop OPERABLE BOC to 3133 =0 1.44 1.47
=1 1.44 1.47 3133 to EOR-5491 =0 1.29 1.32
=1 1.38 1.41 EOR-5491 to EOR-3991 =0 1.30 1.33
=1 1.40 1.43 EOR-3991 to EOC =0 1.33 1.36
=1 1.43 1.46 ONE Turbine Pressure Regulator Out of Service AND Reactor Power between 29.5% and 85%
AND BOTH Turbine Bypass Valves and Moisture Separator Reheater Operable BOC to 3133 =0 1.44 1.47
=1 1.44 1.47 3133 to EOC =0 1.33 1.36
=1 1.43 1.46 Moisture Separator Reheater INOPERABLE BOC to 3133 =0 1.44 1.47
=1 1.48 1.51 3133 to EOC =0 1.37 1.40
=1 1.48 1.51 BOC = Beginning of Cycle EOC = End of Cycle EOR = End of Rated Conditions.
EOR is defined as 100% power, 100% core flow, and all control rods fully withdrawn.
EOR-5491 means 5491 MWD/ST before End of Rated Conditions.
COLR - 22 Revision 0 Page 14 of 30 TABLE 4 (continued) OLMCPR 100/105 AS A FUNCTION OF EXPOSURE AND EXPOSURE CONDITION (MWD/ST) OLMCPR100/105 Turbine Bypass Valve INOPERABLE BOC to 3133 =0 1.44 1.47
=1 1.47 1.50 3133 to EOC =0 1.35 1.38
=1 1.47 1.50 BOTH Turbine Bypass Valve AND Moisture Separator Reheater INOPERABLE BOC to 3133 =0 1.44 1.47
=1 1.50 1.53 INOPERABLE 3133 to EOC =0 1.38 1.41
=1 1.50 1.53 4.3 Calculation of MCPR(P)
MCPR(P), the core power-dependent MCPR operating limit, shall be calculated by the following equation:
( )= x /
KP, the core power-dependent MCPR Operating Limit adjustment factor, shall be calculated by using Section 4.3.1. OLMCPR100/105 shall be determined by interpolation on from Table 3, and shall be calculated by using Section 4.3.2.
4.3.1 Calculation of KP The core power-dependent MCPR operating limit adjustment factor, KP (Reference 2, 3, & 10),
shall be calculated by using one of the following equations:
Note: P = Core power (fraction of rated power times 100) for all calculation of KP.
For 0 < P < 25 :
No thermal limits monitoring is required.
COLR - 22 Revision 0 Page 15 of 30 For 25 < P < 29.5 :
When All Equipment is OPERABLE, For core flow < 50 Mlbs/hr,
. x( . )
=
/
where: KBYP = 1.94 for two loop operation
= 1.97 for single loop operation For core flow 50 Mlbs/hr,
. x( . )
=
/
where: KBYP = 2.13 for two loop operation
= 2.16 for single loop operation For 25 < P < 29.5 : (continued)
When Moisture Separator Reheater is INOPERABLE, For core flow < 50 Mlbs/hr,
. x( . )
=
/
where: KBYP = 1.95 for two loop operation
= 1.98 for single loop operation For core flow 50 Mlbs/hr,
. x( . )
=
/
where: KBYP = 2.13 for two loop operation
= 2.16 for single loop operation When Turbine Bypass is INOPERABLE,
. x( . )
=
/
For core flow or < 50 Mlbs/hr, where: KBYP = 2.35 for two loop operation
= 2.38 for single loop operation
COLR - 22 Revision 0 Page 16 of 30 When Turbine Bypass and Moisture Separator Heater are INOPERABLE, For core flow < 50 Mlbs/hr,
. x( . )
=
/
where: KBYP = 2.35 for two loop operation
= 2.38 for single loop operation For core flow 50 Mlbs/hr,
. x( . )
=
/
where: KBYP = 2.42 for two loop operation
= 2.45 for single loop operation For 29.5 < P < 45 :
= 1.150 + 0.0021 x (45 )
For 45 < P < 60 :
= 1.150 For 60 < P < 85 :
= 1.056 + 0.0038 x (85 )
For 85 < P < 100 :
= 1.000 + 0.0037 x (100 )
KP for Pressure Regulator Out of Service Limits With one Turbine Pressure Regulator Out of Service, Reactor Power greater than 29.5%, and both Turbine Bypass and Moisture Separator Reheater Operable:
For 29.5 < P < 45 :
= 1.303 + 0.0081 x (45 )
For 45 < P < 60 :
= 1.241 + 0.0041 x (60 )
For 60 < P < 85 :
= 1.159 + 0.0033 x (85 )
For Reactor Power < 29.5% and Reactor Power > 85%, the Pressure Regulator Out of Service condition is not limiting (Reference 2).
COLR - 22 Revision 0 Page 17 of 30 4.3.2 Calculation of The value of , which is a measure of the conformance of the actual control rod scram times to the assumed average control rod scram time in the reload licensing analysis (References 4 & 16), shall be calculated by using the following equation:
( ave B )
= A B where: A = 1.096 seconds N1 B = 0.830 + 0.019 x 1.65 n seconds N
i 1 i
n N i i ave = i 1 n
N i 1 i
n = number of surveillance tests performed to date in cycle, Ni = number of active control rods measured in the ith surveillance test, i = average scram time to notch 36 of all rods measured in the ith surveillance test, and N1 = total number of active rods measured in the initial control rod scram time test for the cycle (Technical Specification Surveillance Requirement 3.1.4.4).
The value of shall be calculated and used to determine the applicable OLMCPR100/105 value from Table 3 within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the conclusion of each control rod scram time surveillance test required by Technical Specification Surveillance Requirements 3.1.4.1, 3.1.4.2, and 3.1.4.4.
COLR - 22 Revision 0 Page 18 of 30 4.4 Calculation of MCPR(F)
MCPR(F), the core flow-dependent MCPR operating limit (Reference 2 & 3), shall be calculated by using the following equation:
WT For Two Loop Operation MCPR(F)= MAX( 1.21,( AF + BF ))
100 WT For Single Loop Operation MCPR(F)= MAX( 1.24,( AF + BF ))
100 where:
WT = Core flow (Mlbs/hr).
AF = Given in Table 4.
BF = Given in Table 4.
TABLE 5 FLOW-DEPENDENT MCPR LIMIT COEFFICIENTS Maximum Core Flow*
(Mlbs/hr) AF BF Two Loop Operation 110 -0.596 1.739 Single Loop Operation 110 -0.596 1.769 As limited by the Recirculation System MG Set mechanical scoop tube stop setting.
COLR - 22 Revision 0 Page 19 of 30 5.0 LINEAR HEAT GENERATION RATE TECH SPEC IDENT OPERATING LIMIT 3.2.3 LHGR 5.1 Definition The LINEAR HEAT GENERATION RATE (LHGR) shall be the heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length. By maintaining the operating LHGR below the applicable LHGR limit, it is assured that all thermal-mechanical design bases and licensing limits for the fuel will be satisfied.
5.2 Determination of LHGR Limit The maximum LHGR limit is a function of reactor power, core flow, fuel and rod type, and fuel rod nodal exposure. The limit is developed, using NRC approved methodology described in Reference 7, to ensure the cladding will not exceed its yield stress and that fuel thermal-mechanical design criteria will not be violated during any postulated transient events. The LHGR limit ensures the fuel mechanical design requirements as defined in References 1, 15, & 17 will be met.
The LHGR limit during dual loop operation is calculated by the following equation:
LHGRLIMIT = MIN (LHGR (P), LHGR (F))
where:
LHGR (P) = LHGRFAC (P) x LHGRSTD LHGR (F) = LHGRFAC (F) x LHGRSTD Within four hours after entering single loop operation, the LHGR limit is calculated by the following equation:
LHGRLIMIT = MIN (LHGR (P), LHGR (F))
where:
LHGR (P) = LHGRFAC (P) x LHGRSTD LHGR (F) = LHGRFAC (F) x LHGRSTD LHGRFAC (P) and LHGRFAC (F) are limited to 0.90 The Single Loop Operation multiplier on LHGR is 0.90. (Reference 2)
COLR - 22 Revision 0 Page 20 of 30 LHGRSTD, the standard LHGR limit, is defined at a power of 3486 MWth and flow of 105 Mlbs/hr for each fuel and rod type as a function of fuel rod nodal exposure. LHGRSTD is found in the reference cited in Table 5. When hand calculations are required, LHGRSTD shall be determined by interpolation of the limits provided in the Table 5 reference. LHGRFAC(P), the core power-dependent LHGR limit adjustment factor, shall be calculated by using Section 5.2.1.
LHGRFAC(F), the core flow-dependent LHGR limit adjustment factor, shall be calculated by using Section 5.2.2.
TABLE 6 STANDARD LHGR LIMITS FOR VARIOUS FUEL TYPES For GE14 fuel listed below, the most limiting LHGR for Uranium Only fuel rod is found in NEDC-32868P Revision 6 Table D-2 (References 1 & 15).
For GE14 fuel listed below, the most limiting LHGR for Gadolinia Bearing fuel rods is found in NEDC-32868P Revision 6 Table D-4 (References 1 & 15). Utilize the row for 6% Rod/Section wt-% Gd2O3.
Fuel Types GE14-P10CNAB385-13GZ-100T-150-T6-4571 GE14-P10CNAB384-15GZ-100T-150-T6-4572 GE14-P10CNAB383-13GZ-100T-150-T6-4573 GE14-P10CNAB377-15GZ-100T-150-T6-4574 GE14-P10CNAB383-8G6.0/5G5.0-100T-150-T6-4478 GE14-P10CNAB383-8G6.0/7G5.0-100T-150-T6-4479 GE14-P10CNAB383-2G6.0/11G5.0-100T-150-T6-4480 GE14-P10CNAB383-10G6.0/5G5.0-100T-150-T6-4481
COLR - 22 Revision 0 Page 21 of 30 TABLE 5 (CONT.)
STANDARD LHGR LIMITS FOR VARIOUS FUEL TYPES For GNF3 fuel listed below, the most limiting LHGR for Uranium Only fuel rod is found in NEDC-33879P Revision 2 Table A-1 (References 1 & 17).
For GNF3 fuel listed below, the most limiting LHGR for Gadolinia Bearing fuel rods is found in NEDC-33879P Revision 2 Table A-2 (References 1 & 17). Utilize the row for 6% Rod/Section wt-% Gd2O3.
Fuel Types GNF3-P10CG3B388-14GZ-83AV-150-T6-4661 GNF3-P10CG3B399-14GZ-83AV-150-T6-4662 GNF3-P10CG3B402-16GZ-83AV-150-T6-4663 GNF3-P10CG3B419-16GZ-83AV-150-T6-4664 GNF3-P10CG3B403-16GZ-83AV-150-T6-4888 GNF3-P10CG3B403-15GZ-83AV-150-T6-4889 GNF3-P10CG3B421-13GZ-83AV-150-T6-4890 GNF3-P10CG3B420-13GZ-83AV-150-T6-4891 GNF3-P10CG3B404-16GZ-83AV-150-T6-4892 GNF3-P10CG3B404-14GZ-83AV-150-T6-4893
COLR - 22 Revision 0 Page 22 of 30 5.2.1 Calculation of LHGRFAC(P)
The core power-dependent LHGR limit adjustment factor, LHGRFAC(P) (Reference 2, 3, & 10),
shall be calculated by one of the following equations:
For 0 P < 25 :
No thermal limits monitoring is required.
For 25 P 29.5 :
With All Equipment OPERABLE, or MSR INOPERABLE For core flow < 50 Mlbs/hr, LHGRFAC (P) = 0.568 + 0.00156 (P - 29.5)
For core flow 50 Mlbs/hr, LHGRFAC (P) = 0.568 + 0.00156 (P - 29.5)
With Turbine Bypass INOPERABLE, or Turbine Bypass and MSR INOPERABLE For core flow < 50 Mlbs/hr, LHGRFAC (P) = 0.488 + 0.01067 (P - 29.5)
For core flow 50 Mlbs/hr, LHGRFAC (P) = 0.436 + 0.00511 (P - 29.5)
For 29.5 < P 45 :
LHGRFAC (P) = 0.713 + 0.00529 (P - 45)
For 45 < P 60 :
LHGRFAC (P) = 0.791 + 0.00520 (P - 60)
For 60 < P 85 :
LHGRFAC (P) = 0.922 + 0.00524 (P - 85)
For 85 < P 100 :
LHGRFAC (P) = 1.000 + 0.00520 (P - 100) where: P = Core power (fraction of rated power times 100).
COLR - 22 Revision 0 Page 23 of 30 LHGRFAC(P) for Pressure Regulator Out of Service Limits With one Turbine Pressure Regulator Out of Service and Reactor Power Greater Than or Equal to 25% and both Turbine Bypass and Moisture Separator Reheater Operable:
For 25 P 29.5 :
For core flow < 50 Mlbs/hr, LHGRFAC (P) = 0.568 + 0.00156 (P - 29.5)
For core flow 50 Mlbs/hr, LHGRFAC (P) = 0.568 + 0.00156 (P - 29.5)
For 29.5 < P 45 :
LHGRFAC (P) = 0.680 + 0.00626 (P - 45)
For 45 < P 60 :
LHGRFAC (P) = 0.758 + 0.00520 (P - 60)
For 60 < P 85 :
LHGRFAC (P) = 0.831 + 0.00292 (P - 85)
For 85 < P 100 :
LHGRFAC (P) = 1.000 + 0.00520 (P - 100) where: P = Core power (fraction of rated power times 100).
COLR - 22 Revision 0 Page 24 of 30 5.2.2 Calculation of LHGRFAC(F)
The core flow-dependent LHGR limit adjustment factor, LHGRFAC(F) (Reference 2, 3, & 10),
shall be calculated by the following equation:
WT LHGRFAC(F)= MIN(C, AF + BF )
100 where:
WT = Core flow (Mlbs/hr).
AF = Given in Table 6.
BF = Given in Table 6.
C = 1.0 in Dual Loop and 0.90 in Single Loop.
TABLE 7 FLOW-DEPENDENT LHGR LIMIT COEFFICIENTS Maximum Core Flow*
(Mlbs/hr) AF BF 110 0.8889 0.2613 As limited by the Recirculation System MG Set mechanical scoop tube stop setting.
COLR - 22 Revision 0 Page 25 of 30 6.0 CONTROL ROD BLOCK INSTRUMENTATION TECH SPEC IDENT SETPOINT 3.3.2.1 RBM 6.1 Definition The nominal trip setpoints and allowable values of the control rod withdrawal block instrumentation are shown in Table 7. These values are consistent with the bases of the APRM Rod Block Technical Specification Improvement Program (ARTS) and the MCPR operating limits. (References 2, 5, & 9)
TABLE 8 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS WITH FILTER Setpoint Trip Setpoint Allowable Value Low power setpoint 27.0 28.4 Intermediate power setpoint 62.0 63.4 High power setpoint 82.0 83.4 Low trip setpoint 117.0 118.9 Intermediate trip setpoint 112.2 114.1 High trip setpoint 107.2 109.1 Downscale trip setpoint 94.0 92.3 For this cycle, the analyzed high trip setpoint of 111% bounds the setpoints in Table 7. The OLMCPR associated with the RBM setpoint of 111% is 1.44 for dual loop operation from beginning of cycle to 3133 MWd/st and 1.29 from 3133 MWd/st to the end of cycle. (Reference 2)
COLR - 22 Revision 0 Page 26 of 30 7.0 BACKUP STABILITY PROTECTION REGIONS TECH SPEC REFERENCE OPERATING LIMIT 3.3.1.1 Action Condition J Alternate method to detect and suppress thermal hydraulic instability oscillations TRM REFERENCE OPERATING LIMIT 3.4.1.1 Scram, Exit, and Stability Awareness Regions 7.1 Definition The Backup Stability Protection (BSP) Regions are an integral part of the Tech Spec required alternative method to detect and suppress thermal hydraulic instability oscillations in that they identify areas of the power/flow map where there is an increased probability that the reactor core could experience a thermal hydraulic instability. The BSP Regions are required if the Oscillation Power Range Monitors are inoperable. Regions are identified that are either excluded from planned entry (Scram Region), or where specific actions are required to be taken to immediately leave the region (Exit Region). A region is also identified where operation is allowed provided that additional monitoring is performed to verify that the reactor core is not exhibiting signs of core thermal hydraulic instability (Stability Awareness Region). (Reference 2)
The boundaries of the Scram and Exit regions are established on a cycle specific basis based upon core decay ratio calculations performed using NRC approved methodology.
BSP boundaries for this cycle defined in Figure 1 are applicable when final feedwater temperature is near the optimum range as illustrated in 20.107.02, Loss of Feedwater Heating Abnormal Operating Instruction Enclosure A. Figure 2 is applicable to operation with Feedwater Heaters Out-Of-Service (FWHOOS) or with Final Feedwater Temperature Reduction (FFWTR) or when final feedwater temperature is 15ºF to 55ºF below the optimum range.
COLR - 22 Revision 0 Page 27 of 30 FIGURE 1: BSP REGIONS (NOMINAL FEEDWATER TEMPERATURE)
Nominal feedwater heating exists with all feedwater heaters in service, the moisture separator reheaters in service, and reactor water cleanup in or out of service. Nominal feedwater temperature is determined with the Loss of Feedwater Heating Abnormal Operating Procedure, 20.107.02. If feedwater temperature is less than 15 degrees Fahrenheit below the Optimum Line of the Feedwater Inlet Temperature vs. Reactor Power graph provided in Enclosure A of 20.107.02, then Figure 1 can be used.
COLR - 22 Revision 0 Page 28 of 30 FIGURE 2: BSP REGIONS (FEEDWATER TEMPERATURE REDUCTION)
Reduced feedwater temperature is analyzed for a 55 degree Fahrenheit reduction in feedwater temperature. If feedwater temperature is between 15 degrees Fahrenheit to 55 degrees Fahrenheit below the Optimum Line of the Feedwater Inlet Temperature vs. Reactor Power graph provided in Enclosure A of 20.107.02, then Figure 2 should be used.
COLR - 22 Revision 0 Page 29 of 30
8.0 REFERENCES
Core Operating Limits Report references are cited for two purposes. Many references are used as the basis for information, numbers, and equations found in COLR. These references tend to be fuel type or cycle specific. Other references are listed as basis information for the content and structure of COLR but are not Cycle specific.
- 1. Fuel Bundle Information Report for Fermi 2 Reload 21 Cycle 22, Global Nuclear Fuel, DRF 006N0352, Revision 0, July 2021 (LHGR Limits), DTC: TRVEND, DSN: Cycle 22 FBIR
- 2. Supplemental Reload Licensing Report for Fermi 2 Reload 21 Cycle 22, Global Nuclear Fuel, DRF: 006N0351, Revision 0, July 2021 (MAPLHGR Limits, SLO Multiplier, MCPR Limits, SLMCPR, Off-Rated Limits, Backup Stability Regions, OPRM setpoints, RBM setpoint, PROOS), DTC: TRVEND, DSN: Cycle 22 SRLR
- 3. GNF3 Fuel Design Cycle-Independent Analyses for Fermi 2 Power Plant, GE-Hitachi, 004N7423, Revision 0, November 2019. (GNF3 and GE14 ARTS Limits, RR Pump Seizure, PROOS), Edison File Number: T19-158
- 4. Letter from Greg Porter to B. L. Myers, Scram Times for Improved Tech Specs. GP-99014, October 22, 1999 containing DRF A12-00038-3, Vol. 4 information from G. A.
Watford, GE, to Distribution,
Subject:
Scram Times versus Notch Position (TAU Calculation), Edison File Number: R1-7242
- 5. NUMAC Power Range Neutron Monitoring System (PRNM) Surveillance Validation, Design Calculation DC-4608 Volume 1, Revision G (RBM A and B Setpoints), DTC:
TDPINC, DSN: DC-4608 VOL I
- 6. Detroit Edison Fermi-2 Thermal Power Optimization Task T0201: Operating Power/Flow Map, Edison File Number: T13-050 (P-F Map for BSP figures)
- 7. General Electric Standard Application for Reactor Fuel (GESTAR II), NEDE-24011-P-A, Revision 31 with amendments, Edison File Number: R1-8103
- 8. TRACG Application for Emergency Core Cooling Systems / Loss-of-Coolant-Accident Analyses for BWR/2-6, GE-Hitachi, NEDE-33005P-A, Revision 2, May 2018, DTC:
TRVEND, DSN: NEDE 33005 P A, Edison File Number: R1-8509
- 9. Maximum Extended Operating Domain Analysis for Detroit Edison Company Enrico Fermi Energy Center Unit 2, GE Nuclear Energy, NEDC-31843P, July 1990 (RBM Setpoints) , Edison File Number: R1-7177
COLR - 22 Revision 0 Page 30 of 30
- 10. Fermi 2 TRACG Implementation for Reload Licensing Transient Analysis, Revision 1, 0000-0128-8831-R1, June 2014, (GE14 ARTS Limits), Edison File Number: R1-8124
- 11. Methodology and Uncertainties for Safety Limit MCPR Evaluations, NEDC-32601P-A, August 1999, Edison File Number: R1-7239
- 12. Power Distribution Uncertainties for Safety Limit MCPR Evaluations, NEDC-32694P-A, August 1999, Edison File Number: R1-7240
- 13. R-Factor Calculation Method for GE11, GE12, and GE13 Fuel, NEDC-32505P-A, Revision 1, July 1999, Edison File Number: R1-7238
- 14. Fermi 2 - Issuance of Amendment No. 214 Re: Technical Specifications Task Force (TSTF) TSTF-564, "Safety Limit Minimum Critical Power Ratio" (EPID L-2019-LLA-0028) Letter from Sujata Goetz, NRC, to Peter Dietrich, DTE Electric dated November 5, 2019 (SLMCPR)
- 15. GE14 Compliance with Amendment 22 of NEDE-24011-P-A (GESTAR II), NEDC-32868P, Revision 6, March 2016 (LHGR Limits), Edison File Number: R1-7307
- 16. Letter from G. G. Jones to A. D. Smart, Fermi 2 Technical Specification Changes, February 17, 1989 (Tau)
- 17. GNF3 Generic Compliance with NEDE-24011-P-A (GESTAR II), NEDC-33879P, Revision 2, March 2018 (LHGR Limits), Edison File Number: R1-8483
Analysis, GE-Hitachi, 005N1475, Revision 1, November 2019, Edison File Number: T19-137