NRC-19-0085, DTE Energy Company Transmittal of Revision 1 of the Core Operating Limits Report for Cycle 20

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DTE Energy Company Transmittal of Revision 1 of the Core Operating Limits Report for Cycle 20
ML19354A832
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 12/20/2019
From: Jonathan Haas
DTE Electric Company
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-19-0085
Download: ML19354A832 (29)
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Text

DTE Energy Company 6400 N. Dixie Highway Newport, MI 48166 December 20, 2019 TS 5.6.5 NRC-19-0085 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 Revision 1 of the Core Operating Limits Report for Cycle 20 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 20, Revision 1.

This COLR will be used during the remainder of the Fermi 2 twentieth operating cycle.

No new commitments are being made in this submittal.

Should you have any questions, please contact me at (734) 586-1769.

Sincerely, Jason R. Haas Manager - Nuclear Licensing

Enclosure:

Core Operating Limits Report (COLR), Cycle 20, Revision 1 cc: NRC Project Manager NRC Resident Office Regional Administrator, Region III Michigan Department of Environment, Great Lakes, and Energy

Enclosure to NRC-19-0085 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 Core Operating Limits Report (COLR), Cycle 20, Revision 1

COLR - 20 Revision 1 Page 1 of 27 FERMI 2 CORE OPERATING LIMITS REPORT CYCLE 20 REVISION 1 Prepared by:

Paul R. Kiel ate P ' ' al Technical Expert, Reactor Engineering Reviewed by:

Jere y Mc rew Date Princ al En ineer, Reactor Engineering Approved by: _____//_/_/fdr Michael A. Lake Date Supervisor, Reactor Engineering November 2019

COLR - 20 Revision 1 Page 2 of 27 TABLE OF CONTENTS

1.0 INTRODUCTION

AND

SUMMARY

.....................................................................................4 2.0 SAFETY LIMIT MINIMUM CRITICAL POWER RATIO ................................................... 5 2.1 D efinition ................................................................................................................. 5 2.2 D eterm ination of SLM CPR Lim it ........................................................................... 5 3.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE ............................................. 6 3.1 D efinition ................................................................................................................. 6 3.2 D eterm ination of M APLH GR Lim it........................................................................6 3.2.1 Calculation of MAPFAC(P) ........................................................................ 8 3.2.2 Calculation of MAPFAC(F) ...................................................................... 10 4.0 MINIMUM CRITICAL POWER RATIO..............................................................................11 4.1 D efinition ............................................................................................................... 11 4.2 Determ ination of Operating Lim it MCPR ............................................................. 11 4.3 Calculation of M CPR(P)........................................................................................13 4.3.1 Calculation of KP ....................................................................................... 13 4.3.2 Calculation of t..........................................................................................15 4.4 Calculation of M CPR(F)........................................................................................16 5.0 LINEAR HEAT GENERATION RATE ................................................................................ 17 5.1 D efinition ............................................................................................................... 17 5.2 Determ ination of LH GR Lim it .............................................................................. 17 5.2.1 Calculation of LH GRFA C(P)....................................................................19 5.2.2 Calculation of LH GRFA C(F)....................................................................21 6.0 CONTROL ROD BLOCK INSTRUMENTATION .............................................................. 22 6.1 Definition ............................................................................................................... 22 7.0 BACKUP STABILITY PROTECTION REGIONS .............................................................. 23 7.1 D efinition ............................................................................................................... 23 8.0 REFEREN CES ................................................................................................................ 26

COLR - 20 Revision 1 Page 3 of 27 LIST OF TABLES TABLE 1 FUEL TYPE-DEPENDENT STANDARD MAPLHGR LIMITS.............................7 TABLE 2 FLOW-DEPENDENT MAPLHGR LIMIT COEFFICIENTS.................................10 TABLE 3 OLMCPRioonios AS A FUNCTION OF EXPOSURE AND t..................................12 TABLE 4 FLOW-DEPENDENT MCPR LIMIT COEFFICIENTS ......................................... 16 TABLE 5 STANDARD LHGR LIMITS FOR VARIOUS FUEL TYPES...............................18 TABLE 6 FLOW-DEPENDENT LHGR LIMIT COEFFICIENTS..........................................21 TABLE 7 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS WITH FILTER .................................................................................................................... 22 LIST OF FIGURES FIGURE 1 BSP REGIONS FOR NOMINAL FEEDWATER TEMPERATURE ............. 24 FIGURE 2 BSP REGIONS FOR REDUCED FEEDWATER TEMPERATURE ............. 25

COLR - 20 Revision 1 Page 4 of 27

1.0 INTRODUCTION

AND

SUMMARY

This report provides the cycle specific plant operating limits, which are listed below, for Fermi 2, Cycle 20, 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 SLMCPR 95/95 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 - 20 Revision 1 Page 5 of 27 2.0 SAFETY LIMIT MINIMUM CRITICAL POWER RATIO 2.1 Definition TECH SPEC IDENT OPERATING LIMIT 2.1.1.2 SLMCPR 95/95 The Technical Specification SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (SLMCPR 95/ 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 20)

The Cycle Specific SLMCPR 99.9 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 SLMCPR 99.9,is cycle dependent and ensures 99.9% of the fuel rods in the core are not susceptible to boiling transition. (Reference 20)

The Operating Limit MCPR is set by adding the SLMCPR 99.9 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 SLMCPR 99.9 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 SLMCPR 99.9 values (Reference 2) are:

Two Loop SLMCPR = 1.08 Single Loop SLMCPR = 1.09

COLR - 20 Revision I Page 6 of 27 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:

MAPLHGR.,,T = MIN (MAPLHGR (P), MAPLHGR (F))

where:

MAPLHGR (P) = MAPFAC (P) x MAPLHGRD MAPLHGR (F)=MAPFAC (F) x MAPLHGRSTD Within four hours after entering single loop operation, the MAPLHGR limit is calculated by the following equation:

MAPLHGR,,,,T = MIN (MAPLHGR (P), MAPLHGR (F))

where:

MAPLHGR (P) = MAPFAC (P) x MAPLHGRSD MAPLHGR (F)= MAPFAC (F) x MAPLHGRSD MAPFAC (P) andMAPFAC (F) are limited to 0.80 The Single Loop multiplier limit is 0.80 (Reference 2) based on assuring a LOCA while in single loop will be bounded by the two loop LOCA. (Reference 12)

COLR - 20 Revision 1 Page 7 of 27 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 and 25) 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 19.13 12.82 57.61 8.00 63.50 5.00 Fuel Types 2= GE14-P10CNAB381-4G6.0/11G5.0-100T-150-T6-4372 3= GE14-P10CNAB381-4G6.0/9G5.0-100T-150-T6-4371 4= GE14-P1OCNAB381-15G5.0-100T-150-T6-4373 5= GE14-P1OCNAB381-6G6.0/9G5.0-100T-150-T6-4374 6= GE14-P10CNAB385-13GZ-100T-150-T6-4571 7= GE14-P1OCNAB384-15GZ-100T-150-T6-4572 8= GE14-P10CNAB383-13GZ-100T-150-T6-4573 9= GE14-P10CNAB377-15GZ-100T-150-T6-4574 14 = GE14-P10CNAB376-4G6.0/9G5.0/2G2.0-100T-150-T6-4061 15 = GE14-P10CNAB373-7G5.0/6G4.0-10OT-150-T6-4064 16 = GE14-P10CNAB376-15GZ-100T-150-T6-4063 17 = GE14-P10CNAB379-14GZ-100T-150-T6-4259 18 = GE14-P10CNAB381-4G6.0/1 1G5.0-100T-150-T6-4260 19 = GE14-P10CNAB381-4G6.0/12G5.0-100T-150-T6-4261 20 = GE14-P10CNAB379-15GZ-100T-150-T6-4262 21 = GE14-P10CNAB383-8G6.0/5G5.0-10OT-150-T6-4478 22 = GE14-P10CNAB383-8G6.0/7G5.0-100T-150-T6-4479 23 = GE14-P10CNAB383-2G6.0/11G5.0-100T-150-T6-4480 24 = GE14-P10CNAB383-10G6.0/5G5.0-100T-150-T6-4481

COLR - 20 Revision 1 Page 8 of 27 3.2.1 Calculation of MAPFAC(P)

The core power-dependent MAPLHGR limit adjustment factor, MAPFAC(P) (Reference 2, 3, 11, & 15), 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 Turbine Bypass OPERABLE, For core flow < 50 Mlbs/hr, MAPFAC (P)= 0.604 + 0.0038 (P - 29.5)

For core flow > 50 Mlbs/hr, MAPFAC (P) = 0.584 + 0.0038 (P - 29.5)

With Turbine Bypass INOPERABLE, For core flow < 50 Mlbs/hr, MAPFAC (P)= 0.488 + 0.0051 (P - 29.5)

For core flow > 50 Mlbs/hr, MAPFAC (P)= 0.436 + 0.0051 (P - 29.5)

For 29.5 <P< 100:

MAPFAC (P) =1.0 + 0.005233 (P - 100) where: P = Core power (fraction of rated power times 100).

Note: This range applies with pressure regulator in service and, for power >85%, it also applies with the pressure regulator out of service (PROOS).

COLR - 20 Revision 1 Page 9 of 27 MAPFAC(P) for Pressure Regulator Out of Service Limits With one Turbine Pressure Regulator Out of Service and Reactor Power Greater Than or Equal to 29.5% and Less Than or Equal to 85% and both Turbine Bypass and Moisture Separator Reheater Operable:

For 25 <P < 29.5:

For core flow < 50 Mlbs/hr, MAPFAC (P)= 0.604 + 0.0038 (P - 29.5)

For core flow > 50 Mlbs/hr, MAPFAC (P) = 0.583 + 0.0036 (P- 29.5)

For 29.5<P<45 MAPFAC (P)= 0.680 + 0.00627 (P - 45)

For 45<_P<60 MAPFAC (P)= 0.758 + 0.0052 (P - 60)

For 60 _P 85:

MAPFAC (P) = 0.831 + 0.00292 (P - 85) where: P = Core power (fraction of rated power times 100).

COLR - 20 Revision 1 Page 10 of 27 3.2.2 Calculation of MAPFAC(F)

The core flow-dependent MAPLHGR limit adjustment factor, MAPFAC(F) (Reference 2 & 3),

shall be calculated by the following equation:

MAPFAC(F)=MIN(C, AF X + 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 0.80 in Single Loop.

TABLE 2 FLOW-DEPENDENT MAPLHGR LIMIT COEFFICIENTS Maximum Core Flow*

(Mlbs/hr) AF BF 110 0.6787 0.4358

  • As limited by the Recirculation System MG Set mechanical scoop tube stop setting.

COLR - 20 Revision 1 Page 11 of 27 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 t. t 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 (Reference 2) 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 from the Two Loop OLMCPR.

COLR - 20 Revision 1 Page 12 of 27 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 11)

TABLE 3 OLMCPRioono5 AS A FUNCTION OF EXPOSURE AND T EXPOSURE CONDITION (MWD/ST) OLMCPRioon05 BOTH Turbine Bypass Valves AND Moisture Separator Reheater Two Loop Single Loop OPERABLE BOC to EOR-4991 T=0 1.26 1.29 T=1 1.38 1.41 EOR-4991 to EOR-2991 T=0 1.27 1.30 T=1 1.44 1.47 EOR-2991 to EOC T=0 1.32 1.35 T=1 1.49 1.52 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 EOC T=0 1.32 1.35 T=1 1.49 1.52 Moisture Separator Reheater INOPERABLE BOC to EOC T=0 1.36 1.39 T=1 1.53 1.56 Turbine Bypass Valve INOPERABLE BOC to EOC T=0 1.36 1.39 T=1 1.53 1.56 BOTH Turbine Bypass Valve AND Moisture Separator Reheater INOPERABLE BOC to EOC T =0 1.42 1.45 T =1 1.59 1.62 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-4991 means 4991 MWD/ST before End of Rated Conditions.

COLR - 20 Revision 1 Page 13 of 27 4.3 Calculation of MCPR(P)

MCPR(P), the core power-dependent MCPR operating limit (Reference 2, 3, 11, & 15), shall be calculated by the following equation:

MCPR(P) = KP x OLMCPR 1001 105 Kp, the core power-dependent MCPR Operating Limit adjustment factor, shall be calculated by using Section 4.3.1. OLMCPRoono5 shall be determined by interpolation on t from Table 3, and t 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, 11, &

15), 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.

For 25<P<29.5 :

When Turbine Bypass is OPERABLE, K -- (KBYP +(0.0 32 x (29.5 - P)))

OLMCPR ioon1os For two loop operation, where: KBYP = 2.18 for core flow < 50 Mlbs/hr

= 2.46 for core flow > 50 Mlbs/hr For single loop operation, where: KBYP = 2.21 for core flow < 50 Mlbs/hr

= 2.49 for core flow > 50 Mlbs/hr When Turbine Bypass is INOPERABLE, K=( K BYP + (0.076 x (29.5 - P)))

OLMCPR ioonos For two loop operation, where: KBYP = 2.65 for core flow <50 Mlbs/hr

= 3.38 for core flow > 50 Mlbs/hr For single loop operation, where: KBYP = 2.68 for core flow < 50 Mlbs/hr

= 3.41 for core flow > 50 Mlbs/hr

COLR - 20 Revision 1 Page 14 of 27 For 29.5<P<45 K, = 1.28 + (0.0134 x (45 - P))

For 45:S P < 60 :

KP=1.15+(0.00867 x (60 - P))

KP for Moisture Separator Reheater Operable and Turbine Bypass Valves Operable or Inoperable For 60<P<85:

Kp = 1.065+(0.0034x(85 - P))

For 85<5 P:5 100:

Kp = 1.0+(0.004333x(100 - P))

KP for Moisture Separator Reheater Inoperable and Turbine Bypass Valves Operable or Inoperable For 60< P<85:

K, = 1.076+(0.00296x(85 - P))

For 85<P<100:

Kp = 1.0+(0.00507x(100 - P))

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 K= 1.52 + (0.01193 x (45 - P))

For 45<P<60 K,=1.362+(0.01053x(60-P))

For 60<P<85:

K= 1.217 + (0.0058 x (85 - P))

For 85<P<100:

For Reactor Power > 85%, the Pressure Regulator Out of Service condition is not limiting (Reference 11). Calculate KP using the applicable equations above based on Moisture Separator Reheater and Turbine Bypass Valve operability.

COLR - 20 Revision 1 Page 15 of27 4.3.2 Calculation of'T The value of t, 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 & 24),

shall be calculated by using the following equation:

B)

S= (ave TA -TB where: TA = 1.096 seconds Ni i=1 Tave = '=

Y Ni n = number of surveillance tests performed to date in cycle, Ni = number of active control rods measured in the ith surveillance test, Ti = average scram time to notch 36 of all rods measured in the ith surveillance test, and Ni = 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 t shall be calculated and used to determine the applicable OLMCPRons05 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 - 20 Revision 1 Page 16 of27 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:

For Two Loop Operation MCPR(F)= MAX(1.21, (AF X WT + BF))

100 WT For Single Loop Operation MCPR(F)= MAX(1.24, (AF X -+ BF))

100 where:

WT = Core flow (Mlbs/hr).

AF = Given in Table 4.

BF = Given in Table 4.

TABLE 4 FLOW-DEPENDENT MCPR LIMIT COEFFICIENTS Maximum Core Flow*

(Mlbs/hr) AF BF Two Loop Operation 110 -0.601 1.743 Single Loop Operation 110 -0.601 1.773

  • As limited by the Recirculation System MG Set mechanical scoop tube stop setting.

COLR - 20 Revision I Page 17 of 27 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 & 21 will be met.

The LHGR limit during dual loop operation is calculated by the following equation:

LHGR,,,, = MIN (LHGR (P), LHGR (F))

where:

LHGR (P) = LHGRFAC (P) x LHGRTD LHGR (F) = LHGRFAC (F) x LHGR,,

Within four hours after entering single loop operation, the LHGR limit is calculated by the following equation:

LHGR,,T = MIN (LHGR (P), LHGR (F))

where:

LHGR (P) = LHGRFAC (P) x LHGRSD LHGR (F) = LHGRFAC (F)x LHGRSTD LHGRFAC (P) and LHGRFAC (F) are limited to 0.80 The Single Loop multiplier limit is 0.80 (Reference 2) based on assuring a LOCA in single loop will be bounded by the two loop LOCA (Reference 12).

COLR - 20 Revision 1 Page 18 of 27 LHGRsm, 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. LHGRTD is found in the reference cited in Table 5. When hand calculations are required, LHGRsmD 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 5 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 & 21).

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 & 21). Utilize the row for 6% Rod/Section wt-%

Gd 2O3.

Fuel Types 2= GE14-P10CNAB381-4G6.0/11G5.0-100T-150-T6-4372 3= GE14-P10CNAB381-4G6.0/9G5.0-100T-150-T6-4371 4= GE14-P10CNAB381-15G5.0-100T-150-T6-4373 5= GE14-P10CNAB381-6G6.0/9G5.0-100T-150-T6-4374 6= GE14-P10CNAB385-13GZ-100T-150-T6-4571 7= GE14-P10CNAB384-15GZ-100T-150-T6-4572 8= GE14-P10CNAB383-13GZ-100T-150-T6-4573 9= GE14-P1OCNAB377-15GZ-100T-150-T6-4574 14 = GE14-P10CNAB376-4G6.0/9G5.0/2G2.0-100T-150-T6-4061 15 = GE14-P10CNAB373-7G5.0/6G4.0-100T-150-T6-4064 16 = GE14-P10CNAB376-15GZ-100T-150-T6-4063 17 = GE14-P10CNAB379-14GZ-100T-150-T6-4259 18 = GE14-P10CNAB381-4G6.0/11G5.0-100T-150-T6-4260 19 = GE14-P10CNAB381-4G6.0/12G5.0-100T-150-T6-4261 20 = GE14-P10CNAB379-15GZ-100T-150-T6-4262 21 = GE14-P10CNAB383-8G6.0/5G5.0-100T-150-T6-4478 22 = GE14-P10CNAB383-8G6.0/7G5.0-100T-150-T6-4479 23 = GE14-P10CNAB383-2G6.0/1 1G5.0-100T-150-T6-4480 24 = GE14-P10CNAB383-10G6.0/5G5.0-100T-150-T6-4481

COLR - 20 Revision 1 Page 19 of 27 5.2.1 Calculation of LHGRFAC(P)

The core power-dependent LHGR limit adjustment factor, LHGRFAC(P) (Reference 2, 3, 11, &

15), 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 Turbine Bypass OPERABLE, For core flow < 50 Mlbs/hr, LHGRFAC (P) = 0.604 + 0.0038 (P - 29.5)

For core flow > 50 Mlbs/hr, LHGRFAC (P) = 0.584 + 0.0038 (P - 29.5)

With Turbine Bypass INOPERABLE, For core flow < 50 Mlbs/hr, LHGRFAC (P) = 0.488 + 0.0051 (P - 29.5)

For core flow > 50 Mlbs/hr, LHGRFAC (P) = 0.436 + 0.0051 (P - 29.5)

For 29.5 <P < 100:

LHGRFAC (P) = 1.0 + 0.005233 (P - 100) where: P = Core power (fraction of rated power times 100).

Note: This range applies with pressure regulator in service and, for power >85%, it also applies with the pressure regulator out of service.

COLR - 20 Revision 1 Page 20 of 27 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 29.5% and Less Than or Equal to 85% and both Turbine Bypass and Moisture Separator Reheater Operable:

For 25 < P 29.5:

For core flow < 50 Mlbs/hr, MAPFAC (P)= 0.604 + 0.0038 (P - 29.5)

For core flow > 50 Mlbs/hr, MAPFAC (P)= 0.583 + 0.0036 (P - 29.5)

For 29.5<P<45 LHGRFAC (P) = 0.680 + 0.00627 (P - 45)

For 45<P<60 LHGRFAC (P) = 0.758 + 0.0052 (P - 60)

For 60<P<85:

LHGRFAC (P) = 0.831 + 0.00292 (P - 85) where: P = Core power (fraction of rated power times 100).

COLR - 20 Revision I Page 21 of 27 5.2.2 Calculation of LHGRFAC(F)

The core flow-dependent LHGR limit adjustment factor, LHGRFAC(F) (Reference 2 & 3), shall be calculated by the following equation:

WT' LHGRFAC(F)=MIN(C, AF x -+ 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 0.80 in Single Loop.

TABLE 6 FLOW-DEPENDENT LHGR LIMIT COEFFICIENTS Maximum Core Flow*

(Mlbs/hr) AF BF 110 0.6787 0.4358

  • As limited by the Recirculation System MG Set mechanical scoop tube stop setting.

COLR - 20 Revision 1 Page 22 of27 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, & 10)

TABLE 7 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 1.26 for dual loop operation.

COLR - 20 Revision I Page 23 of 27 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 (refer to Figures 1 and 2) 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. 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 below the optimum range.

COLR - 20 Revision 1 Page 24 of 27 Figure 1 - BSP Regions for Nominal Feedwater Temperature 80 100%CLTP =3486MWt Rated CoreFlow = 100.0 Mlb/hr MELLLA RodLine 70 Approx. Natural Circulation 60 ---- - - - - - --- - - - - - -

Region Exit so - - -- -- Rg on Stability -

Awareness Region a 40...-

OPRM Enabled Region 3 0--- ----

20 30 40 50 60 Percent (%)of Rated Core Flow 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 - 20 Revision 1 Page 25 of 27 Figure 2 - BSP Regions for Reduced Feedwater Temperature 80 100%CLTP =3486MWt Rated CoreFlow =100.0Mlb/hr MELLLA RodLine 70 ___ --- --

Approx. Natural Circulation 60 - - - -- -- - - - - - -

Scram Region Exit Stability 50 soRegion Awareness Region L

c 40 ---

Enabled Region 30 - - - ----- _ _- - -- - - - - -- - - - -

20 30 40 50 60 Percent (%)of Rated CoreFlow Reduced feedwater temperature is analyzed for a 50 degree Fahrenheit reduction in feedwater temperature. If feedwater temperature is more 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 2 can be used.

COLR - 20 Revision I Page 26 of 27

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 Enrico Fermi 2 Reload 19 Cycle 20," Global Nuclear Fuel, DRF 004N4270, Revision 0, July 2018 (LHGR Limits), DTC: TRVEND, DSN: Cycle 20 FBIR
2. "Supplemental Reload Licensing Report for Enrico Fermi 2 Reload 19 Cycle 20," Global Nuclear Fuel, DRF: 004N4269, Revision 0, July 2018 (MAPLHGR Limits, SLO Multiplier, MCPR Limits, SLMCPR, Off-Rated Limits, Backup Stability Regions, OPRM setpoints, RBM setpoint), DTC: TRVEND, DSN: Cycle 20 SRLR
3. "GE14 Fuel Cycle-Independent Analyses for Fermi Unit 2", GE-NE-0000-0025-3282-00 dated November 2004 (ARTS Limits equations, RR Pump Seizure)
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 27 with amendments
8. "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident - SAFER/GESTR Application Methodology," NEDE 23785-1-PA, Revision 1, October 1984
9. "Fermi-2 SAFER/GESTR-LOCA, Loss-of-Coolant Accident Analysis," NEDC-31982P, July 1991, and Errata and Addenda No. 1, April 1992
10. "Maximum Extended Operating Domain Analysis for Detroit Edison Company Enrico Fermi Energy Center Unit 2," GE Nuclear Energy, NEDC-31843P, July 1990

COLR - 20 Revision I Page 27 of 27

11. Fermi 2 Pressure Regulator Out of Service Evaluation - Verified Final Report, Letter 1-2LHRMS-4 dated February 10, 2011. DTC: TRVEND, DSN: 1-2LHRMS-4 Edison File Number: R1-8100 (PROOS Limits)
12. "DTE Energy Enrico Fermi 2 SAFER/PRIME-LOCA Loss of Coolant Accident Analysis" DRF: 000N1319-RO dated March 2015
13. Letter from T. G. Colburn to W. S. Orser, "Fermi Amendment No. 87 to Facility Operating License No. NPF-43 (TAC NO. M82102)," September 9, 1992
14. Letter from J. F. Stang to W. S. Orser, "Amendment No. 53 to Facility Operating License No. NPF-43: (TAC No. 69074)," July 27, 1990
15. "Fermi 2 TRACG Implementation for Reload Licensing Transient Analysis", Revision 1, 0000-0128-8831-R1, June 2014, Edison File Number: R1-8124
16. Methodology and Uncertainties for Safety Limit MCPR Evaluations, NEDC-32601P-A, August 1999
17. Power Distribution Uncertainties for Safety Limit MCPR Evaluation, NEDC-32694P-A, August 1999
18. R-Factor Calculation Method for GEl 1, GE12, and GE13 Fuel, NEDC-32505P-A, Revision 1, July 1999
19. "Turbine Control Valve Out-Of-Service for Enrico Fermi Unit-2," GE - Nuclear Energy, GE-NE-J11-03920-07-01, October 2001
20. "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)

21. "GE14 Compliance with Amendment 22 of NEDE-2401 1-P-A (GESTAR II)", NEDC-32868P, Revision 6, March 2016 (LHGR Limits), Edison File Number: R1-7307
22. "Fermi 2 - Issuance of Amendment Re: Measurment Uncertainty Recapture Power Uprate (TAC No. MF0650)" Letter from Thomas Wengert, NRC, to Joseph Plona, DTE Electric dated February 10, 2014
23. Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors -

Volume 1, NEDO-24154-A, August 1986, Edison File Number: R1-7389.

24. Letter from G. G. Jones to A. D. Smart, "Fermi 2 Technical Specification Changes,"

February 17, 1989

25. "Cycle Management Report for Fermi-2 Cycle 20," 004N4278 Revision 0, October 2018 Edison File Number: R1-8497 (Fuel Type Table)
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