ML20078J978
| ML20078J978 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 09/13/1994 |
| From: | Myers R, Rubley G, Thorson L DETROIT EDISON CO. |
| To: | |
| Shared Package | |
| ML20078J975 | List: |
| References | |
| NUDOCS 9411220119 | |
| Download: ML20078J978 (15) | |
Text
COLR 5 Revision 0 Page 1 of 15 FERMI 2 j
CORE OPERATING L,IMITS REPORT CYCLE 5 Prepared by:
I A9-A44Y G. A. Rubley Date Senior Engineer - Nuclear Fuel Reviewed by:
SA 'l
- d. [ Myers
'8 Date Principal Engineer - Nuclear Fuel
&f3 of94-J. M. Thdrson Date Reactor Engineer C 7-~
9-2M L. JVFrasson Date COLR Checklist Reviewer Approved by:
MW do-
+0 /M
[-/ 3-ff S. T-C Hsieh 6
Date Supervisor - Nuclear Fuel AUGUST 1994 9411220119 941117 PDR ADOCK 05000341 P
COLR-5 Revision 0 Page 2 of 15 TABLE OF CONTENTS
1.0 INTRODUCTION
AND
SUMMARY
4 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE..........
5 2.1 Definition 5
2.2 Determir.ation of MAPLHGR Limit..
5 2.2.1 Calculation of MAPFAC(P)...
7 2.2.2 Calculation of MAPFAC(F).....
8 i
i 3.0 MINIMUM CRITICAL POWER RATIO 9
3.1 Definition 9
3.2 Determination of Operating Limit MCPR...........
9 3.3 Calculation of MCPR(P) 10 3.3.1 Calculation of K, 11 3.4 Calculation of MCPR(F) 12 4.0 LINEAR HEAT GENERATION RATE 13
)
4.1 Definition 13 4.2 Detennination of LHGR Limit.
13 5.0 CONTROL ROD BLOCK INSTRUMENTATION.
14 5.1 Definition 14
6.0 REFERENCES
15 I
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COLR-5 Revision 0 Page 3 of 15 LIST OF TABLES TABl.E1 FUEL TYPE-DEPENDENT STANDARD MAPLHGR LIMITS 6
TABLE 2 FLOW-DEPENDENT MAPLHGR LIMIT COEFFICIENTS...
8 TABLE 3 OLMCPR,3 AS A FUNCTION OF EXPOSURE AND 7 10 3
TABLE 4 FLOW-DEPENDENT MCPR LIMIT COEFFICIENTS 12 TABLE 5 LIIGR LIMITS FOR VARIOUS FUEL TYPES 13 TABLE 6 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS WITH FILTER.
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COLR-5 Revision 0 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 5, 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.2aAw 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.8 This evaluation determined the necessary adjustments which are 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 licensed operating domain."
OPERATING LIMIT TECHNICAL SPECIFICATION APLIIGR 3/4.2.1 MCPR 3/4.2.3 LIIGR 3/4.2.4 RBM 3/4.3.6 APLIIGR = AVERAGE PLANAR LINEAR HEAT GENERATION RATE MCPR
= MINIMUM CRITICAL POWER RATIO LilGR
= LINEAR IIEAT GENERATION RATE RBM
= ROD BLOCK MONITOR SETPOINTS l
COLR-5 Revision 0 Page 5 of 15 2.0 AVERAGE PLANAR I.1NEAR HEAT GENERATION RATE TECH SPEC IDENT OPERATING LIMIT 3/4.2.1 APLHGR 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 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 oower, core flow, lattice type. and average planar exposure. The limit is developed to ensure gross cladding failure will not occur following a loss of coolant accident (LOCA) and that fuel thermal-mechanical design cciteria 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 be met.
The MAPLHGR limit is calculated by the following equation:
AfAPLHGR
,,7= AflN( AfAPLHGR (P), AL4PLHGR (F))
w where:
AfAPLHGR(P) = AfAPFAC(P) x AL4PLHGl$m AL4PLUGR (F) = AfAPFAC (F) x AfAPLHGlkm MAPLHGRg, the standard MAPLHGR limit, is defined at a power of 3430 MWt and flow of 105 Mibs /hr for each fuel type as a function of average planar exposure and is presented in 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 re required as specified in Tec'mical Specification 3/4.2.1, MAPLHGR shall be determined s73 by interpolation from Table 1.
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COLR-5 Revision 0 Page 6 of 15 MAPEA XP), 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.
j-TABLE 1 FUEL TYPE-DEPENDENT STANDARD MAPLHGR LIMITS i
Standard MAPLHGR Limit 1
(KW/FT)
Exposure (GWD/ST)
Fuel Type 1
1 1
i 6
2 0.0 12.02 10.82 10.84 10.82 11.73 11.51 0.2 12.00 10.90 10.92 10.90 11.79 11.54 1.0 12.10 12.14 11.10 11.11 11.10 11.90 11.62 2.0 11.36 11.38 11.36 12.01 11.71 3.0 11.64 11.66 11.64 12.10 11.79 40 11.94 11.83 11.94 12.20 11.87 5.0 12.70 12.93 12.17 12.02 12.17 12.30 11.%
60 12.30 12.18 12.30 12.40 12.04 7.0 12.48 12.38 12.48 12.51 ~
12.13 8.0 13.28 12.68 12.61 12.68 12.62 12.23
' 9.0 12.88 12.84 12.88 12.68 12.34 10.0 12.80 13.34 13.04 13.02 13.04 12.70 12.48 12.5 13.33 13.07 13.07 13.07 12.57 12.50 15.0 12.90 13.02 12.83 12.83 12.83 12.17 12.19 1
17.5 11.78 11.82 20.0 12.70 12.18 12.18 12.18 11.39 11.45 25.0 t I.70 11.75 11.54 11.54 11.54 10.63 10.71 30.0 10.80 9.91 9.99 35.0 10.26 10.26 10.26 9.24 9.28 40.0 9.00 8.62 8.59 45.0 9.05 8.76 8.72 8.76 8.03 7.91 30.0 6.64 7.45 7.24 30.66 5.88 50.76 5.88 5.88 55.0 6.84 6.56 Fuel Types I = P8CIB176-4GZ-100M-150-T 5 = SVEA-96 2 = GE8B-P8CQB318-7GZ-100M-4WR-150-T 6 = GE11-P9 CUB 331-IIGZ-100M-146-T 3 = GE98-P8CWB-321-9GZ 80M-150-T 7 = GE11-P9 CUB 353-10GZ-100M-146-T 4 = GE9B-P8CWB-321-10GZ-80M-150-T
COLR-5 Revision 0 Pcge 7 of 15 2.2.1 Calculation of MAPFAC(P)
The core power-dependent MAPIlIGR limit adjustment factor, MAPFAC(P), shall be calculated by one of the following equations:
For 0 s P < 25 :
No thermal limits monitoring is required.
4 For 25 s P < 30 :
I With turbine bypass OPERABLE, For core flow s 50 Mlbs/hr, A/APFAC(P)= 0.606 + 0.0038 (P-30) i For core flow > 50 Mlbs/hr, AIAPFAC(P) = 0.586 + 0.0038 (P-30)
With turbine bypass INOPERABLE, For core flow s 50 Mlbs/hr, MAPFAC(P) = 0.490 + 0.0050 (P-30)
For core flow > 50 Mlbs/hr, AIAPFAC(P) = 0.438 + 0.0050 (P-30)
For 30 s P s 100 -
AIAPFAC(P) = 1.0 + 0.005224(P-100) where:
P = Core power (fraction of rated power times 100).
)
1 1
l COLR-5 Revision 0 -
i Page 8 of 15 2.2.2. Calculation of MAPFAC(F) j The core flow-dependent MAPLHGR limit adjustment factor, MAPFAC(F), shall be calculated by the following equation:
MAPFAC(F) = MIN (1.0, A, x
+ B,)
100 where:
WT = Core flow (Mibs /hr).
A, = Given in Table 2.
B, = Given in Table 2.
4 TAHLE 2 FLOW-L)EPENDENT MAPLHGR LIMIT COEFFICIENTS J
Maximum Con Flow *
(Mlbs/hr)
A, B,
110 0.6800 0.4340
'As limited by the Recirculation System scoop tube setting.
t
COLR-5 Revision 0 Page 9 of 15 3.0 MINIMUM CRITICAL POWER RATIO TECH SPEC IDENT OPERATING LIMIT 3/4.2.3
- MCPR 3.1 Definition The CRITICAL POWER RATIO (CP.R) 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 required Operating Limit MCPR (OLMCPR) at steady-state rated power and flow operating conditions is derived from the established fuel cladding integrity Safety I.imit 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:
OLAfCPR = A(AX(AfCPR (P), AfCPR (F))
MCPR(P), the core power-dependent MCPR operating limit, shall be calculated using i
Section 3.3.
I MCPR(F), the core flow 4ependent 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.
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4 COLR - 5 Revision 0 Page 10 of 15 3.3
. Calculation of MCPR(P)
MCPR(P), the core power-dependent MCPR operating limit, shall be calculated by the following equation:
MCPR(F) = K, x OLMCP%,u OLMCPR,,g shall be determined by interpolation from Table 3, and 7 shall by calculated by using Technical Specification Section 3/4.2.3.
K,,, the core power-dependent MCPR Operating Limit adjustment factor, shall be calculated by using Section 3.3.1.
TABLE 3 OLMCPR,,, AS A FUNCTION OF FXPOSURE AND 7 n
EXPOSURE CONDITION (MWD /ST)
!)L8 9X9 10X10 Both Turbine Bypass and GE6, GE8, GE9 Gell SVEA-96 Moisture Separator Reheater OPERABLE BOC to $500 y=0 1.25 1.28 1.50 r=1 1.25 1.33 1.50 4
5500 to EOC r=0 1.25 1.33 L50 r=1 1.28 1.41 1.55 2
Either Turbine Bypass or Moisture Separator Reheater INOPERABLE BOC to EOC r=0 1.27 1.36 1.54 r=1 1.31 1.44 1.60 Both Turbine Bypass and Moisture Separator Reheater INOPERABLE BOC to EOC r=0 1.29 1.41 1.57 t=1 1.32 1.49 1.62
..n
.. =..
COLR-5 Revision 0 Page 11 of 15 3.3.1. Calculation of K, ihe core power-dependent MCPR operating limit adjustment factor, K,, shall be calculated by using one of the following equations:
For 0 s P < 25 -
No thermal limits monitoring is required.
For 25 s P < 30 :
When turbine bypass is OPERABLE, K
+ (0.026 x (30-P))
err A,f
=
OLMCP Q o, where:
K,y, = 1.90 for core Dow s 50 Allbs/hr -
= 2.23 for core Dow > 50 Allbs/hr When turbine bypass is INOPERABLE, K
+ (0.054 x (30-P))
f37 A,f
=
OLMCPl%o, where:
K,y, = 2.26 for core Dow s 50 Allbs/hr
= 3.03 for core Dow > 50 Allbs/hr For 30 s P < 45 :
K, = 1.28 + (0.0134 x (45 -P))
For 45 s P < 60 :
K, = 1.15 + (0.00867 x (60-P))
For 60 s P s 100 :
K, = 1.0 + (0.00375 x (100-P))
where:
P== Core power (fraction of rated power times 100).
st
COLR-5 Revision 0 Page 12 of 15 3.4 Calculation of MCPR(F)
MCPR(F), the core flow-dependent MCPR operating limit, shall be calculated by using one of the following equations:
For MT < 40 :
f AICPR(F) = (A,x
+ B ) x (1.0 + 0.0032 x (40 - 157))
r 100 For WT 2: 40 :
AfCPR(F) = AIAX(l.'20, A,x 'S + B,)
100 where:
WT = Core flow (Mlbs/hr).
A = Given in Table 4.
r B = Given in Table 4.
y TABLE 4 FLOW-DEPENDENT MCPR LIMIT COEFFICIENTS Maximum Core Flow *
(Mlbs/hr)
A B
r r
110
-0.600 1.731
- As limited by the Recirculation System scoop tube setting.
.~
o
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COLR-5 Revision 0 Page 13 of 15 j
4.0 LINEAR HEAT GENERATION RATE j
TECH SPEC IDENT OPERATING ' LIMIT i
3/4.2.4 LIIGR 4.1 Definition The LINEAR llEAT GENERATION RATE (LHGR) shall be the heat generation 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 UO, pellets and Zircaloy cladding are different in that, dtiring heatup, the fuel pellet could come into contact with the cladding and create stress.
By maintaining the operating LIIGR below the limits stated in Table 5 and the operating MAPLIIGR 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 LilGR LIMIT P8CIB176-4GZ-100M-150-T 13.4 KW/FT GE81bP8CQB318 7GZ-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 SVEA-96 14.4 KW/FT gel 1 P9 CUB 331-1IGZ-100M-146-T 14.4 KW/FT gel 1-P9 CUB 353-10GZ-100M-146-T 14.4 KW/FT 4
.n
--p
4 COLR-5 Revision 0
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Page 14 of 15 5.0 CONTROL ROD BLOCK INSTRUMENTATION TECH SPEC IDENT SETPOINT
)
i 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 Iect'nical 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 IIPSP 82.0 83.6 i
LTSP 117.0 118.8 ITSP 112.2 114.0 IITSP 107.2 109.0 DTSP 94.0 92.3 where:
LPSP 12)w power setpoint; Rod Block Monitor (RBM) System trip automatically bypassed below this level IPSP Intermediate power setpoint IIPSP liigh power setpoint LTSP Low trip setpoint ITSP Intermediate trip setpoint llTSP Iligh trip setpoint DTSP Downscale trip setpoint i
COLR - 5 Revision 0 Page 15 of 15
6.0 REFERENCES
1,
" General Electric Standard Application for Reactor Fuel (GESTAR H)," NEDE-1 24011-P-A, Revision 10, 2.
"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.
3.
" Fermi-2 SAFER /GESTR-LOCA, Loss-of-Coolant Accident Analysis,"
NEDC-31982P, July 1991, Errata and Addenda, April 1992.
4.
" Lattice-Dependent MAPLHGR Report for Fermi Power Plant Unit 2 Reload 4 Cycle 5," GE Nuclear Energy,23A7226AA, Rev. O.
5.
" Supplemental Reload Licensing Report for Fermi Power Plant Unit 2 Reload 4, Cycle 5," GE Nuclear Energy,23A7226, Revision 0, December 1993.
6.
Letter from G. D. Plotycia to G. A. Rubley, " Fermi 2, Cycle 5 - Core Redesign Safety Evaluation," GDP:94-147, June 22,1994.
7.
Letter from G. D. Plotycia to G. A. Rubley, " Detroit Edison Questions Regarding the Femti 2, Cycle 5 - Core Redesign Safety Evaluation," GDP:94-178, July 29,1994.
8.
" Supplemental Lead Fuel Assembly Licensing Report, SVEA-96 LFAs to Fermi-2 Summary," ABB Atom, BR 90-003, October 1990.
4 9.
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, i
10.
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.
11.
" Safety Evaluation Core Operating Limits Report Cycle 5 Revision 0," G. A. Rubley, SE-94-0080.
12.
" Maximum Extended Operating Dornain Analysis for Detroit Edison Company Enrico Fermi Energy Center Unit 2," GE Nuclear Energy, NEDC31843P, July 1990.
13.
Letter from R. J. Howard to M. K. Deora and H. L. Hubeny, " Operating Flow Dependent MCPR and MAPLHGR Thermal Limits," TDEC-PE-134, September 30,1990 14.
" Power Range Neutron Monitoring System," J. L. Leong, DC-4608, Vol. IX DCD, Rev. O, September 29,1992.
15.
Letter from G. D. Plotycia to G. A. Rubley, " Fermi-2, Cycle 5 Nuclear Design 2
Information," GDP:94-182, August 5,1994.
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