NRC-12-0070, Transmittal of Core Operating Limits Report, Cycle 16, Revision 1

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Transmittal of Core Operating Limits Report, Cycle 16, Revision 1
ML12279A042
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 10/04/2012
From: Rad Z
Detroit Edison
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
NRC-12-0070
Download: ML12279A042 (27)
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Text

Fermi 2 6400 North Dixie Hwy., Newport, MI 48166 Detroit Edison~

A/I TS 5.6.5 October 4, 2012 NRC-12-0070 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555-0001

Reference:

Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43

Subject:

Transmittal of Core Operating Limits Report, Cycle 16, Revision 1 In accordance with Fermi 2 Technical Specification 5.6.5, Detroit Edison hereby submits a copy of the Core Operating Limits Report (COLR), Cycle 16, Revision 1.

This COLR will be used during the Fermi 2 sixteenth operating cycle.

Should you have any questions or require additional information, please contact me at (734) 586-5076.

Sincerely, Zackary W. Rad Manager, Nuclear Licensing A DTE Energy Company

USNRC NRC-12-0070 Page 2 Enclosure cc: NRC Project Manager Reactor Projects Chief, Branch 4, Region III NRC Resident Office Regional Administrator - Region III Supervisor, Electric Operators, Michigan Public Service Commission [w/o Enclosure]

ENCLOSURE TO NRC-12-0070 CORE OPERATING LIMITS REPORT CYCLE 16 REVISION 1

COLR - 16 Revision 1 Page 1 of 24 FERMI 2 CORE OPERATING LIMITS REPORT CYCLE 16 REVISION 1 Prepared by: /7 12 Rich d eck Date Engineer, Reactor Engineering Reviewed by: _ _ _ _ _

Paul Kiel ate Technical Expert, Reactor Engineering Approved by: A.2,J A4 _____

Michael Lake Date Supervisor, Reactor Engineering September 2012

COLR - 16 Revision 1 Page 2 of 24 TABLE OF CONTENTS

1.0 INTRODUCTION

AND

SUMMARY

...................................................................4 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE.............................................5 2 .1 D efinition ..................................................................------.--....-................................. 5 2.2 Determination of MAPLHGR Limit....................................5 2.2.1 Calculation of M APFAC(P) ....................................................................... 7 2.2.2 Calculation of MAPFAC(F) ........................................................................ 8

...... 9 3.0 MINIMUM CRITICAL POWER RATIO............................

3.1 Definition.................................................--.................. ........... 9 3.2 Determination of Operating Limit MCPR ........................................ .. 9 3.3 Calculation of MCPR(P)............................................................11 3.3.1 Calculation of Kp .............................................................................. .11 3.3.2 Calculation oft ...................................... 13 3.4 Calculation of MCPR(F).....................................14 15 4.0 LINEAR HEAT GENERATION RATE ................................................................................

4.1 D efinition ....................................................................... ..................................... 15 Determination of LHGR Lim it .............................................................................. 15 4.2 4.2.1 Calculation of LHGRFAC(P)...................................................................17 4.2.2 Calculation of LHGRFAC(F)....................................................................18 19 5.0 CONTROL ROD BLOCK INSTRUMENTATION ..........................

5.1 Definition..........................................................................19 20 6.0 BACKUP STABILITY PROTECTION REGIONS ..............................................................

6.1 D efinition .......................................................................................... 20

7.0 REFERENCES

.................................................................................... 23

COLR - 16 Revision 1 Page 3 of 24 LIST OF TABLES TABLE 1 FUEL TYPE-DEPENDENT STANDARD MAPLHGR LIMITS.............................6 TABLE 2 FLOW-DEPENDENT MAPLHGR LIMIT COEFFICIENTS...................................8 TABLE 3 OLMCPRioon 1 o5 AS A FUNCTION OF EXPOSURE AND 't..................................10 TABLE 4 FLOW-DEPENDENT MCPR LIMIT COEFFICIENTS ......................................... 14 TABLE 5 STANDARD LHGR LIMITS FOR VARIOUS FUEL TYPES...............................16 TABLE 6 FLOW-DEPENDENT LHGR LIMIT COEFFICIENTS.........................................18 TABLE 7 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS WITH FILTER .................................................................................................................... 19 TABLE 8 BSP REGION DESCRIPTIONS..............................................................................21 LIST OF FIGURES FIGURE 1 BSP REGIONS FOR NOMINAL FEEDWATER TEMPERATURE ............. 21 FIGURE 2 BSP REGIONS FOR REDUCED FEEDWATER TEMPERATURE ............. 22

COLR - 16 Revision 1 Page 4 of 24

1.0 INTRODUCTION

AND

SUMMARY

This report provides the cycle specific plant operating limits, which are listed below, for Fermi 2, Cycle 16, 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 TECINICAL SPECIFICATION APLHGR 3.2.1 MCPR 3.2.2 LHGR 3.2.3 RBM 3.3.2.1 BSP REGIONS 3.3.1.1 APLHGR = AVERAGE PLANAR LINEAR HEAT GENERATION RATE MCPR = MINIMUM CRITICAL POWER RATIO LHGR = LINEAR HEAT GENERATION RATE RBM = ROD BLOCK MONITOR SETPOINTS BSP = BACKUP STABILITY PROTECTION

COLR - 16 Revision 1 Page 5 of 24 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 2.1 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 fuel bundle at the height.

2.2 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:

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

where:

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

MAPLHGR,,Ir = MIN (MAPLHGR (P), MAPLHGR (F), MAPLHGR (SLO))

where:

M4PLHGR (SLO) =1.0 x MAPLHGRSTD The Single Loop multiplier is 1.0 since the off-rated ARTS limits bound the single loop MAPLHGR limit. (Reference 2)

COLR - 16 Revision 1 Page 6 of 24 MAPLHGRsTD, the standard MAPLHGR limit, is defined at a power of 3430 MWt 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, MAPLHGRsTm shall be determined by interpolation from Table 1. MAPFAC(P), the core power-dependent MAPLHGR limit adjustment factor, shall be calculated by using Section 2.2.1. MAPFAC(F), the core flow-dependent MAPLHGR limit adjustment factor, shall be calculated by using Section 2.2.2.

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 1= GE14-P10CNAB400-16GZ-100T-150-T6-2787 11= GE14-P10CNAB375-13G5-100T-150-T6-3339 3 = GE14-P1OCNAB380-10G5/4G4-100T-150-T6-2868 12= GE14-P10CNAB376-15G5-100T-150-T6-3340 4 = GE14-P10CNAB381-7G5/8G4-100T-150-T6-2869 13 = GE14-P1OCNAB375-14G5-100T-150-T6-3338 6= GE14-P10CNAB381-7G5/8G4-100T-150-T6-2869 14= GE14-P1OCNAB376-4G6/9G5/2G2-10OT-150-T6-4061 7 = GE14-P10CNAB381-16G5-100T-150-T6-2999 15 = GE14-P1OCNAB373-7G5/6G4-10OT-150-T6-4064 8= GE14-P10CNAB380-4G6/9G5-100T-150-T6-3150 16 = GE14-P10CNAB376-15GZ-100T-150-T6-4063 9 = GE14-P1OCNAB380-7G5/8G4-100T-150-T6-3152 10 = GE14-P1OCNAB378-14GZ-100T-150-T6-3151

COLR - 16 Revision 1 Page 7 of 24 2.2.1 Calculation of MAPFAC(P)

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

11), shall be calculated by one of the following equations:

For 0 <P <25:

No thermal limits monitoring is required.

For 25 <P < 30:

With turbine bypass OPERABLE, For core flow < 50 Mlbs/hr, MAPFAC (P)= 0.606 + 0.0038 (P- 30)

For core flow > 50 Mlbs/hr, MAPFAC (P)=0.586 + 0.0038 (P- 30)

With turbine bypass INOPERABLE, For core flow < 50 Mlbs/hr, MAPFAC (P)= 0.490 + 0.0050 (P - 30)

For core flow > 50 Mlbs/hr, MAPFAC (P)=0.438 + 0.0050 (P- 30)

For 30<P<100:

MAPFAC (P)=1.0 + 0.005224 (P- 100) where: P = Core power (fraction of rated power times 100).

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

COLR - 16 Revision 1 Page 8 of 24 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 30% and Less Than or Equal to 85% and both Turbine Bypass and Moisture Separator Reheater Operable:

For 30<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).

2.2.2 Calculation of MAPFAC(F)

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

shall be calculated by the following equation:

WT MAPFAC(F) = MIN(1.0, AF x--+BF) 100 where:

WT = Core flow (Mlbs/hr).

AF = Given in Table 2.

BF = Given in Table 2.

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

(Mlbs/hr) AF BF 110 0.6787 0.4358

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

COLR - 16 Revision 1 Page 9 of 24 3.0 MINIMUM CRITICAL POWER RATIO TECH SPEC IDENT OPERATING LIMIT 3.2.2 MCPR 3.1 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 assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

3.2 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. ti is a measure of scram speed, and is defined in Section 3.3.2. Cycle 16 operating limits are based on the Dual Loop SLMCPR of 1.08.

The OLMCPR shall be calculated by the following equation:

OLMCPR = MAX(MCPR(P), MCPR(F))

MCPR(P), the core power-dependent MCPR operating limit, shall be calculated using Section 3.3.

MCPR(F), the core flow-dependent MCPR operating limit, shall be calculated using Section 3.4.

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. However, OLMCPR is not increased when operating in single loop due to inherent conservatism.

COLR - 16 Revision 1 Page 10 of 24 In case of operation with one Turbine Pressure Regulator out of service, OLMCPR limits are bounding when reactor power is less than 30% or greater than 85%. When reactor power is greater than or equal to 30% 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 OLMCPRio 10 s AS A FUNCTION OF EXPOSURE AND 'T (Reference 2 and 22)

EXPOSURE CONDITION (MWD/ST) OLMCPR100 /105 Both Turbine Bypass and Two Loop Single Loop Moisture Separator Reheater OPERABLE BOC to 6182 T=0 1.29 1.29 T=1 1.46 1.46 6182 to 7782 T=O 1.33 1.33 t=1 1.50 1.50 7782 to EOC T=O 1.33 1.33 T=1 1.50 1.50 One Turbine Pressure Regulator Out of Service and Reactor Power Greater Than or Equal to 30%

and Less Than or Equal to 85% and both Turbine Bypass and Moisture Separator Reheater Operable BOCtoEOC T=0 1.33 1.33 T=1 1.50 1.50 Moisture Separator Reheater INOPERABLE BOCtoEOC T=0 1.35 1.35 T =1 1.52 1.52 Turbine Bypass INOPERABLE BOC to EOC 'C=0 1.34 1.34

'T= 1 1.51 1.51 Both Turbine Bypass and Moisture Separator Reheater INOPERABLE BOC to EOC 'C= 0 1.37 1.37

'C = 1 1.54 1.54

COLR - 16 Revision 1 Page 11 of 24 3.3 Calculation of MCPR(P) shall be MCPR(P), the core power-dependent MCPR operating limit (Reference 2, 3 & 11),

calculated by the following equation:

MCPR(P) = K x OLMCPRIoo1 os Kp, the core power-dependent MCPR Operating Limit adjustment factor, shall be calculated by using Section 3.3.1.

OLMCPRioolios shall be determined by interpolation on c from Table 3 (Reference 2), and t

shall be calculated by using Section 3.3.2.

3.3.1 Calculation of Kp The core power-dependent MCPR operating limit adjustment factor, Kp (Reference 2, 3, & 11),

shall be calculated by using one of the following equations:

For 0 <P <25 No thermal limits monitoring is required.

For 25<P<30 :

When turbine bypass is OPERABLE, K =(KYP + (0.032 x (30-)))

OLMCPR 1oonos where: KBYP = 2.16 for core flow <50 Mlbs/hr

= 2.44 for core flow >50 Mlbs/hr When turbine bypass is INOPERABLE,

- P)))

KP = (KBYP +(0.076 x (30 OLMCPR ioonos where: KBYP =2.61 for core flow < 50 Mlbs/hr

= 3.34 for core flow > 50 Mlbs/hr

COLR - 16 Revision 1 Page 12 of 24 For 30<P<45 KP = 1.28 + (0.0134 x (45 - P))

For 45<P<60 KP = 1.15 + (0.00867 x (60 - P))

For 60<P<100:

KP = 1.0 + (0.00375 x (100 - P))

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 Kp for Pressure Regulator Out of Service Limits With one Turbine Pressure Regulator Out of Service and Reactor Power Greater Than or Equal to 30% and Less Than or Equal to 85% and both Turbine Bypass and Moisture Separator Reheater Operable:

For 30<P<45 KP =1.52+(0.01193x (45-P))

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

For 60 <P <85:

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

where: P = Core power (fraction of rated power times 100).

COLR - 16 Revision 1 Page 13 of 24 3.3.2 Calculation of T to The value of t, which is a measure of the conformance of the actual control rod scram times the assumed average control rod scram time in the reload licensing analysis (Reference 4), shall be calculated by using the following equation:

ave TB S

TA - TB where: ZA= 1.096 seconds N1 TB = 0.830 + 0.019 x 1.65 seconds Y N 1=1 Nin rave YNi 1=1 n = number of surveillance tests performed to date in cycle, N = number of active control rods measured in the i* surveillance test, 2i = average scram time to notch 36 of all rods measured in the it surveillance test, and N = 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).

value The value of t shall be calculated and used to determine the applicable OLMCPRioonos scram time surveillance test 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 required by Technical Specification Surveillance Requirements 3.1.4.1, 3.1.4.2, and 3.1.4.4.

COLR - 16 Revision 1 Page 14 of 24 3.4 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 MCPR(F)= MAX(1.21,(AF K---+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 Single or Two Loop 110 -0.601 1.743

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

COLR - 16 Revision 1 Page 15 of 24 4.0 LINEAR HEAT GENERATION RATE TECH SPEC IDENT OPERATING LIMIT 3.2.3 LHGR 4.1 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.

4.2 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 References 7 and 8, 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 Reference 1 will be met.

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

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

where:

LHGR (P)= LHGRFAC (P) x LHGRsr LHGR (F)=LHGRFAC (F) x LHGRsD LHGRTD, the standard LHGR limit, is defined at a power of 3430 MWt and flow of 105 Mlbs/hr for each fuel and rod type as a function of fuel rod nodal exposure and is presented in Table 5. Table 5 contains only the most limiting Gadolinia LHGR limit for the maximum allowed Gadolinia concentration of the applicable fuel product line. (Reference 1) When hand calculations are required, LHGRSTD shall be determined by interpolation from Table 5.

LHGRFAC(P), the core power-dependent LHGR limit adjustment factor, shall be calculated by using Section 4.2.1. LHGRFAC(F), the core flow-dependent LHGR limit adjustment factor, shall be calculated by using Section 4.2.2.

COLR - 16 Revision 1 Page 16 of 24 TABLE 5 STANDARD LHGR LIMITS FOR VARIOUS FUEL TYPES GE14 Most Limiting GE14 Uranium Only Fuel Rods Gadolinia Bearing Fuel Rods Exposure LHGR Exposure LHGR GWD/ST KW/FT GWD/ST KW/FT 0.0 13.40 0.0 12.26 14.51 13.40 12.28 12.26 57.61 8.00 55.00 7.32 63.50 5.00 60.84 4.57 Fuel Types 1= GE14-P10CNAB400-16GZ-100T-150-T6-2787 11= GE14-P1OCNAB375-13G5-100T-150-T6-3339 3 = GE14-P10CNAB380-10G5/4G4-100T-150-T6-2868 12 = GE14-P1OCNAB376-15G5-100T-150-T6-3340 4 =GE14-P1OCNAB381-7G5/8G4-100T-150-T6-2869 13= GE14-P10CNAB375-14G5-100T-150-T6-3338 6 = GE14-P10CNAB381-7G5/8G4-100T-150-T6-2869 14 = GE14-P1OCNAB376-4G6/9G5/2G2-100T-150-T6-4061 7 = GE14-P10CNAB381-16G5-100T-150-T6-2999 15 = GE14-P10CNAB373-7G5/6G4-100T-150-T6-4064 8 = GE14-P10CNAB380-4G6/9G5-100T-150-T6-3150 16 = GE14-P10CNAB376-15GZ-100T-150-T6-4063 9 = GE14-P10CNAB380-7G5/8G4-100T-150-T6-3152 10 = GE14-P10CNAB378-14GZ-100T-150-T6-3151

COLR - 16 Revision 1 Page 17 of 24 4.2.1 Calculation of LHGRFAC(P)

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

shall be calculated by one of the following equations:

For 0 < P <25:

No thermal limits monitoring is required.

For 25 < P < 30:

With turbine bypass OPERABLE, For core flow < 50 Mlbs/hr, LHGRFAC(P)= 0.606 + 0.0038 (P - 30)

For core flow > 50 Mlbs/hr, LHGRFAC (P)= 0.586 + 0.0038 (P - 30)

With turbine bypass INOPERABLE, For core flow < 50 Mlbs/hr, LHGRFAC (P)= 0.490 + 0.0050 (P - 30)

For core flow > 50 Mlbs/hr, LHGRFAC (P) = 0.438 + 0.0050 (P- 30)

For 30<P<100:

LHGRFAC (P)= 1.0 + 0.005224 (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 - 16 Revision 1 Page 18 of 24 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 30% and Less Than or Equal to 85% and both Turbine Bypass and Moisture Separator Reheater Operable:

For 30<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).

4.2.2 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(1. 0, AF X -+ BF) 100 where:

WT = Core flow (Mlbs/hr).

AF = Given in Table 6.

BF = Given in Table 6.

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 - 16 Revision 1 Page 19 of 24 5.0 CONTROL ROD BLOCK INSTRUMENTATION TECH SPEC IDENT SETPOINT 3.3.2.1 RBM 5.1 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, 6, & 10).

TABLE 7 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS WITH FILTER Setpoint Trip Setpoint Allowable Value LPSP 27.0 28.4 IPSP 62.0 63.4 HPSP 82.0 83.4 LTSP 117.0 118.9 ITSP 112.2 114.1 HTSP 107.2 109.1 DTSP 94.0 92.3 where:

LPSP Low power setpoint; Rod Block Monitor (RBM) System trip automatically bypassed below this level IPSP Intermediate power setpoint HPSP High power setpoint LTSP Low trip setpoint ITSP Intermediate trip setpoint HTSP High trip setpoint DTSP Downscale trip setpoint

COLR - 16 Revision 1 Page 20 of 24 6.0 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 6.1 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. Regions are identified (refer to Table 8 and 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 these regions are established on a cycle specific basis based upon core decay ratio calculations performed using NRC approved methodology. The Cycle 16 regions are valid to a cycle exposure of 11,209 MWd/st (Reference 21).

These regions are only applicable when the Oscillation Power Range Monitoring System (OPRM) is inoperable. The Cycle 16 region boundaries defined in Figure 1 are applicable when final feedwater temperature is in 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 - 16 Revision 1 Page 21 of 24 TABLE 8 BSP REGION DESCRIPTIONS Region: Nominal Feedwater Temperature Reduced Feedwater Temperature Scram Region: >98% Rod Line, < 43% Flow > 89% Rod Line, <50% Flow Exit Region: > 68% Rod Line, <41% Flow > 68% Rod Line, < 41% Flow

> 77% Rod Line, <48% Flow > 77% Rod Line, <51% Flow

> 102% Rod Line, <50% Flow > 102% Rod Line, < 55% Flow Stability Awareness > 58% Rod Line, < 46% Flow > 58% Rod Line, < 46% Flow Region > 72% Rod Line, <53% Flow > 71% Rod Line, < 56% Flow

> 88% Rod Line, < 55% Flow > 85% Rod Line, < 60% Flow Table 8 values are conservatively rounded FIGURE 1- BSP REGIONS FOR NOMINAL FEEDWATER TEMPERATURE 80 100% CLTP =3430 MWt MELLLA Rod Line 70 RatedCoreFlow =100.0Mlb/hr c ~Py Approx. Natural Circulation abilit C 60 \S Scram Region Exit Region 4 0 0

r 40 40 50 60 30 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 Instruction, 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 of Enclosure A of 20.107.02, Loss of Feedwater Heating, then Figure 1 shall be used if the Oscillation Power Range Monitor is out of service.

COLR - 16 Revision 1 Page 22 of 24 FIGURE 2 - BSP REGIONS FOR REDUCED FEEDWATER TEMPERATURE 80 100%CLTP =3430MWt R~ated Core Flow =100.0 Mlb/hrE MLLARdin 70 Approx. Natural Circulation

\ Stability Awareness Scram Regio

.40 0

30 40 50 60 Percent (%) of Rated Core Flow Reduced feedwater temperature is analyzed for a 50 degree Fahrenheit reduction in feedwater below temperature at 100% power. If feedwater temperature is more than 15 degrees Fahrenheit the Optimum Line of the Feedwater Inlet Temperature vs. Reactor Power graph of Enclosure A of 20.107.02, Loss of Feedwater Heating, then Figure 2 shall be used if the Oscillation Power Range Monitor is out of service.

Inlet Figure 2 is valid until feedwater temperature meets the Minimum Line of the Feedwater Temperaure vs Ractor Power graph of Enclosure A of 20.107.02, Loss of Feedwater Heating.

COLR - 16 Revision 1 Page 23 of 24

7.0 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 because they are basis information for the content and structure of COLR but are not Cycle specific.

1. "Fuel Bundle Information Report for Enrico Fermi 2 Reload 15 Cycle 16," Global Nuclear Fuel, 0000-0131-0566-FIBR, Revision 0, January 2012 (LHGR Limits)
2. "Supplemental Reload Licensing Report for Enrico Fermi 2 Reload 15 Cycle 16," Global Nuclear Fuel, 0000-0131-0566-SRLR, Revision 0, January 2012 (MAPLHGR Limits, SLO Multiplier, MCPR Limits, SLMCPR, Off-Rated Limits, Backup Stability Regions, OPRM setpoints, RBM setpoint)
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)

5. CSCCD-C51 K622/C51 R809C Revision 2, "Programming for Rod Block Monitor (RBM-A)

PIS # C51K622 and Operator Display Assembly (ODA) PIS # C51R809C" (RBM A Setpoints)

6. CSCCD-C51 K623/C51 R809D Revision 2, "Programming for Rod Block Monitor (RBM-B)

PIS # C51K623 and Operator Display Assembly (ODA) PIS # C51R809D" (RBM B Setpoints)

7. "General Electric Standard Application for Reactor Fuel (GESTAR II)," NEDE-2401 1-P-A, Revision 18 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 (P-F Map for BSP figures)

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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/GESTR Loss of Coolant Accident Analysis for GE14 Fuel" GE-NE-0000-0030-6565 Revision 1 dated June 2008
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. "Power Range Neutron Monitoring System,", DC-4608, Vol. XI DCD, Rev. B and DC-4608 Vol. I Rev. D.
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 GE11, 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. Letter from David P. Beaulieu (USNRC) to William T. O'Connor, Jr. (Detroit Edison),

"Fermi Issuance of Amendment RE: Changes to the Safety Limit Minimum Critical Power Ratio (TAC NO. MC4748)," dated November 30, 2004 (SLMCPR Limit)

21. Cycle 16 Stability Information, DTC: TRVEND DSN: Cycle 16 Stability, Edison File No:

R1-8125 (Stability Limiting Exposure)

22. "Cycle Management Report Supplement 1 for FERMI-2 Cycle 16," Global Nuclear Fuel, 0000-0151-7891-CMR, Revision 0, August 2012 (OLMCPR Exposure Points)
23. Long Term Operation at 70% Power with a Single Feedwater Pump, July 2012, DTC:

TDEVAL DSN: TE-J11-12-059, Revision 0

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