ML20044G438

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Rev 1 to Fermi 2 Colr,Cycle 4.
ML20044G438
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 05/25/1993
From: Hsieh S, Myers B, Rubley G
DETROIT EDISON CO.
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ML20044G435 List:
References
NUDOCS 9306030087
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       ".                                                       COLR - 4 Revision 1 Page 1 of 15 FERMI 2 CORE OPERATING LIMITS REPORT CYCLE 4                                          :

r Prepared by: It/ M-%i - 93 G. A. Rubley Date Senior Engineer - Reactor Physics Reviewed by: # f'23'93 B.'L. @ers 9 Date Principal Engineer - Reactor Engineering W . fw 5-25-13 L. JMFrasson Date COLR Checklist Reviewer Approved by: 0 M r zr-73 S. T-C Hsieh Date Supervisor - Nuclear Fuel MAY 1993 93060300e7 930527 DR ADDCK 0500 1

.. . .- - .- .. - - . . . ~ , ., 9 COLR'- 4 ' ' Revisioa 1

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TABLE OF CONTENTS 

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1.0 INTRODUCTION

AND

SUMMARY

, . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4                                     ;

2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE . . . . . . . . . . . . . 5' , 2.1 Definition .......................................5 2.2 Determination of MAPLHGR Limit . . . . . . . . . . . . . . . . . . . . . . . . 5 2.2.1 Calculation of MAPFAC(P) ........................;71 2.2.2 Calculation of MAPFAC(F) ........................~8 .; 

                                                                                                                                  .t 3.0 MINIMUM CRITICAL POWER RATIO                    ..........................                                :9-            -

3.1 Definition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9_ , 3.2 Determination of Operating Limit MCPR , . . . . . . . . . . . . . . . . . . . . 9- -l 3.3 Calculation of MCPR(P) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 - . 3.3.1 Calculation of K, . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 j 3.4 Calculation of MCPR(F) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12  ! 4.0 LINEAR HEAT GENERATION RATE ..........................13 . 4.1 Definition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 '  : 4.2 Determination of LHGR Limit .......................... 13-5.0 CONTROL ROD BLOCK INSTRUMENTATION . . . . . . . . . . . . . . . . . . . . . 14-5.1 Definition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ; 14 . l i

6.0 REFERENCES

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15                      ,

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COLR - 4 Revision ! 

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LIST OF TABLES TABLE 1 FUEL TYPE-DEPENDENT STANDARD MAPLHGR LIMITS ...... 6 TABLE 2 FLOW-DEPENDENT MAPLHGR LIMIT COEFFICIEffrS . . . . . . . . . 8 TABLE 3 OLMCPRm3o3 AS A FUNCTION OF EXPOSURE AND r ......... 10 TABLE 4 FLOW-DEPENDENT MCPR LIMIT COEFFICIENTS . . . . . . . . . . . 12 TABLE 5 LHGR LIMITS FOR VARIOUS FUEL TYPES ...............13 TABLE 6 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS WITH l FILTER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 P

COLR - 4 . Revision 1 Page 4 of 15

1.0 INTRODUCTION

AND

SUMMARY

This report provides the cycle specific plant operating limits, which are listed below, for Fermi 2, Cycle 4, as required by Technical Specifications 6.9.3. The analytical methods used _to determine these core operating limits are those previously reviewed and approved by the Nuclear Regulatory Commission in GESTAR II.i.2.3As 1 For the SVEA-96 lead fuel assemblies, an evaluation of the differences between SVEA-96 and the Cycle 3 GE9 reload bundles has been performed.6 This evaluation determined the necessary adjustments which wer needed to account for the physical differences between the two bundle types. The cycle specific limits contained within this report are valid for the full range of the Maximum Extended Operating Domain (MEOD). OPERATING IMH1 TECHNICAL SPECIFICATION APLHGR 3/4.2.1 MCPR 3/4.2.3 LHGR 3/4.2.4 RBM 3/4.3.6 APLHGR = AVERAGE PLANAR LINEAR HEAT GENERATION RATE MCPR = MINIMUM CRITICAL POWER RATIO LHGR = LINEAR HEAT GENERATION RATE RBM = ROD BLOCK MONITOR SETPOINTS l 

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COLR ' 4 Revision 1 Page 5 of 15 1 2.0 AVERAGE PLANAR LINEAR IIEAT GENERATION RATE :l q TECH SPEC IDENT OPERATING LIMIT f l 3/4.2.1 APLHGR j i 2.1 Definition The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) shall be applicable to a specific planar height and is equal to averaging the LINEAR HEAT .i GENERATION RATE over each fuel rod in the plane. . 2.2 Determination of MAPLHGR Limit , The maximum APLHGR (MAPLHGR) limit is a function of reactor power, core flow, lattice i type, and average planar exposure. The limit is developed to ensure gross cladding failure will- 3 not occur following a loss of coolant accident (LOCA) and that fuel thermal-mechanical design criteria will not be violated during any postulated transient events. 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 1 and 2 will -l be met. l. The MAPLHGR limit is calculated by the following equation: MAPLHGRm = MIN (MAPLHGR(P), MAPLHGR(F) ) where: ) i MAPLHGR(P) = MAPFAC(P)

  • MAPLHGR, MAPLHGR(F) = MAPFAC(F)
  • MAPLHGRg  ;

MAPLHGRrro, 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 j Table 1. Since fuel types may contain more than one lattice type (axially), Table 1 represents the most limiting lattice type at each exposure point for that fuel type. When hand calculations are required as specified in Technical Specification 3/4.2.1, MAPLHGRsro shall be determined by interpolation from Table 1. 

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COLR - 4 Revision 1 Page 6 of 15 MAPFAC(P), the com 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 LBilTS Standard MAP 1.HGR Limit (KW/FT) Exposure (GWD/ST) Fuel Type 2 8 1 2 1 a i f 0.0 12.02 11.99 10.82 10.84 10.82 11.73 0.2 12.00 11.90 10.90 10.92 10.90 11.79 1.0 12.10 12.00 12.14 12.10 11.10 11.11 11.10 11.90 2.0 1136 1138 11.36 12.01 3.0 11.64 11.66 11.64 12.10 4.0 11.94 11.88 11.94 12.20 5.0 12.70 12.10 12.93 12.79 12.17 12.02 12.17 12.30 60 1230 12.18 12.30 12.40 7.0 12.48 1238 12.48 12.51 8.0 13.28 13.15 12.68 12.61 12.68 12.62 9.0 12.88 12.84 12.88 12.68 10.0 12.80 12.20 1334 13.34 13.04 13.02 13.04 12.70 12.5 1333 1332 13.07 13.07 13.07 12.57 15.0 12.90 12.20 13.02 13.02 12.83 12.83 12.83 12.17 17.5 11.78 20.0 12.70 12.10 12.18 12.18 12.18 11.39  ; 25.0 11.70 11.60 11.75 11.75 11.54 11.54 11.54 10.63 30.0 10.80 11.20 9.91 35.0 10.26 10.26 10.26 9.24 40.0 9.00 930 8.62 45.0 9.05 9.04 8.76 8.72 8.76 8.03 50.0 6.64 6.63 7.45 50.66 5.88 50.76 5.88 5.88 55.0 6.84 56.83 6.60 Fuel Types 1 = PSCIB176-4GZ-100M-150-T .5 = GE9B-P8CWB321-9GZ-80M-150-T 2 = P8CIB219-4GZ-100M-150-T 6 = GE9B-P8CWB321-10GZ-80M-150-T 3 = GE8B-P8CQB318-7GZ-100M-4WR-150-T 7 = SVEA-96  ! 4 = GE8B-P8CQB318-7GZ1-100M-4WR-150-T 8 = GE11-P9 CUB 331-11GZ-100M-146-T -; 4 f J f

COLR - 4 Revision 1 Page 7 of 15 2.2.1 Calculation of MAPFAC(P) The core power-dependent MAPLHGR limit adjustment factor, MAPFAC(P), shall be calculated by one of the following equations: For 01 P < 25 : No thermal limits monitoring is required. For 25 A P < 30 : With turbine hvoass OPERABLE, For core flow A 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 bvoass INOPERABLE, For core flow i 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).

COLR - 4 Revision 1 Page 8 of 15 1 i 2.2.2 Calculation of MAPFAC(F) . 1 The core flow-dependent MAPLHGR 1imit adjustment factor, MAPFAC(F), shall be calculated by the following equation: 3 MAPFAC(F) = bHN (1.0, A,< # + B,) 100 where: WT = Core flow (Mlbs/hr). Ap = Given in Table 2. , By = Given in Table 2. r TABLE 2 FLOW-DEPENDENT MAPLIIGR LIMIT COEFFICIENTS Maximum Core Flow (Mlbs/hr) A, B, 117.0 0.6886 0.3828 112.0 0.6807 0.4214 110.0 0.6800 0.4340 107.0 0.6758 0.4574 102.5 0.6784 0.4861 l E f i I

l COLR - 4 Revision 1 Page 9 of 15 3.0 MINIMUAf CRITICAL POWER RATIO TECH SPEC IDENT OPERATING LIMIT 3/4.2.3 MCPR f 3.1 Definition The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in the assembly which is calculated by application of an NRC approved critical power correlation to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power. The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR that exists in the core. . 3.2 Determination of Operating Limit MCPR The requimd Operating Limit MCPR (OLMCPR) at steady-state rated power and flow operating conditions is derived from the established fuel cladding integrity Safety Limit MCPR of 1.07 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. Two different core average exposure conditions are evaluated. The result is an Operating Limit MCPR which is a function of exposure and 7. 7 is a measure of scram speed, and is defined in Technical Specification Section 3/4.2.3. 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 is increased by 0.01, but OLMCPR does not change.  ; 

                   =

F 

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                    .                                                                                  COLR - 4 Revision 1 Page 10 of 15 3.3     Calculation of MCPR(P)                                                                                            :

MCPR(P), the core power-dependent MCPR opemting limit, shall be calculated by the following equation: 1 MCPR(P) = K,

  • OLMCPRm,w  :

OLMCPRmios hall s be determined by interpolation from Table 3, and r shall by calculated by i using Technical Specification Section 3/4.2.3. l Kp, the core power-dependent MCPR Operating Limit adjustment factor, shall be calculated by ') using Section 3.3.1. j u TABLE 3 OLMCPR fios AS A FUNCTION OF EXPOSURE AND tc 3 OLMCPR 3 g.,- a CONDITION EXPOSURE -3 (MWD /ST) EXE .PX9. 10X10 .. Both Turbine Bypass and GE6, GES, GE9 Gell SVEA-% .;j 

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Moisture Separator Reheater ' OPERABLE BOC to 6500 r=0 1.26 1.33 1.53 r=1 1.28 1.38 '1.55 1-6500 to EOC r=0 1.28 1.38 1.55  : r=1 1.32 1.46 1.62 : .! 

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Either Turbine Bypass or 5 Moisture Separator Reheater . 

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INOPERABLE BOC to EOC r=0 _ 1.32 1.41 1.62- .j t=1 1.36 1.49 1.69. j j Both Turbine Bypass and i Moisture Separator Reheater INOPERABLE - _ BOC to EOC r = _0 1.34 1.44 1.65 ll 7 = 1. 1.37 1.52 '1.70 . S 

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COLR - 4 Revision 1 Page 11 of 15 3.3.1 Calculation of Kr The core power-dependent MCPR operating limit adjustment factor, Kp, shall be calculated by using one of the following equations: For 0 1 P < 25 : No thermal limits monitoring is required. For 25 A P < 30 : When turbine bypass is OPERABLE, Karr + (0.026 * (30- P)) A,f = OLMCPR noonos where: Kay, = 1.90 for core flow 150 Mlbs/hr 

                        = 2.23 for core flow > 50 Mlbs/hr When turbine bypass is INOPERABLE,
                                    =

Karr + (0.054 * (30-P)) A,f OLMCPRm 1c, where: Kay, = 2.26 for core flow 150 Mlbs/hr 

                        = 3.03 for core flow > 50 Mlbs/hr For 30 1 P < 45 :

K, = 1.28 + (0.0134 * (45-P)) For 45 i P < 60 . K, = 1.15 + (0.00867 * (60-P)) For 60 < P < 100 : K, = 1.0 + (0.00375 + (100-P)) where: P = Core power (fraction of rated power times 100).

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Page 12 of 15 i 3.4 Calculation of MCPR(F) 4 MCPR(F), the com flow-dependent MCPR operating limit, shall be calculated by using one of l the following equations: i For WT < 40 : f MCPR(F) = (A f

  • WT + B f ) * (1.0 + 0.0032*(40-WI))

100 I For WT _> 40 : MAX (1.20, fA

  • WT +B) f  ;

100 t f where: WT = - Core flow (Mlbs/hr). l Ap = Given in Table 4. .{ By = Given in Table 4. t TABLE 4 FLOW-DEPENDENT MCPR LIMIT COEFFICIENTS .:; Maximum Core Flow ' (Mlbs/hr) Ag B, i 117.0 -0.632 1.809 112.0 -0.602- 1.747  ; 110.0 -0.600 1.731 107.0 -0.586 1.697- 1 102.5 -0.571 1.655 .j 1 

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COLR - 4 Revision 1 Page 13 of 15 4.0 LINEAR HEAT GENERATION RATE TECU SPEC IDENT OPERATING LIhUT 3/4.2.4 LHGR 4.1 Definition The LINEAR HEAT GENERATION RATE (LHGR) shall be the heat genention per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length. 4.2 Determination of LHGR Limit The thermal expansion rates of UO2 Pellets and Zircaloy cladding are different in that, during heatup, the fuel pellet could come into contact with the cladding and create stress. By maintaining the operating LHGR below the limits stated in Table 5 and the operating MAPLHGR below those stated in Section 2.0, it is assured that all thermal-mechanical design bases and licensing limits for the fuel will be satisfied. TABLE 5 LHGR LIMITS FOR VARIOUS FUEL TYPES FUEL TYPE LHGR LIMIT P8CIB176-4GZ-100M-150-T 13.4 KW/FT P8CIB219-4GZ-100M-150-T 13.4 KW/FT GE8B-P8CQB318-7GZ-100M-4WR-150-T 14.4 KW/FT GE8B-P8CQB318-7GZl-100M-4WR-150-T 14.4 KW/FT ' GE9B-P8CWB321-9GZ-80M-150-T 14.4 KW/FT GE9B-P8CWB321-10GZ-80M-150-T 14.4 KW/FT  ! Gell-P9 CUB 331-llGZ-100M-146-T 14.4 KW/FT SVEA-96 14.4 KW/FT l l l i

COLR - 4 Revision 1 Page 14 of 15 5.0 CONTROL ROD BLOCK INSTRUMENTATION TECII SPEC IDENT SETPOINT 3/4.3.6 RBM 5.1 Definition The nominal trip setpoints and allowable values of the control rod withdrawal block instrumentation for use in Technical Specification 3/4.3.6 are shown in Table 6. These values are consistent with the bases of the APRM Eod Block Technical Specification Improvement Program (ARTS) and the MCPR operating limits. TABLE 6 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS WITH FILTER Setpoint Trip Setpoint Allowable Value LPSP 27.0 28.6 IPSP 62.0 63.6 HPSP 82.0 83.6 LTSP 117.0 118.8 ITSP 112.2 114.0 HTSP 107.2 109.0 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 - 4 Revision 1 Page 15 of 15 6.0 REFERFA'CES

1. " General Electric Standard Application for Reactor Fuel (GESTARII)," NEDE-24011-P-A, Revision 10.
2. "The GESTR-LOCA and SAFER Models for the Evaluation of the less-of-Coolant Accident - SAFER /GESTR Application Methodology," NEDE 23785-1-PA, Revision 1,  ;

October 1984.

3. " Fermi-2 SAFER /GESTR-LOCA,Ioss-of-Coolant Accident Analysis," NEDC-31982P, .

July 1991, Errata and Addenda, April 1992. l

4. " Supplemental Reload Licensing Submittal for Fermi Power Plant Unit 2 Reload 3, Cycle 4," GE Nuclear Energy, 23A7175, Revision 0, April 1992.
5. Letter from G. D. Plotycia to H. L. Hubeny, " Fermi 2, Cycle 4 - Licensing Evaluation 1

of Modified Operating Strategy," GDP:93-101, May 20,1993.

6. " Supplemental Lead Fuel Assembly Licensing Repon, SVEA,96 LFAs to Fermi-2 Summary," ABB Atom, BR 90-003, October 1990.
7. Ietter from G. D. Plotycia to J. E. Morrison, " Fermi-2, Cycle 4 Reanalysis with Modified Turbine Control Valve Position," GDP:92-198, September 10,1992.
8. Letter from T. G. Colburn to W. S. Orser, " FERMI AMENDMENT NO. 87 TO i FACILITY OPERATING LICENSE NO. NPF-43 (TAC NO. M82102)," September 9, 1992.

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