ML20211P011
| ML20211P011 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/08/1997 |
| From: | Myers B, Rubley G, Thorson J DETROIT EDISON CO. |
| To: | |
| Shared Package | |
| ML20211P010 | List: |
| References | |
| NUDOCS 9710200032 | |
| Download: ML20211P011 (17) | |
Text
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FERMI 2 CORE OPERATING LIMITS REPORT CYCLE 6 i
information and Procedures DSN Revision DCR#
DTC File #
COLR Cycle 6 i
N/A TMTRM 1754.01 IP Code Date Approved Released By Date Issued Recipient 9710200032 971014 PDR ADOCK 05000341 P
COLR - 6 Revision 1 Page 1 of 16 FERMI 2 CORE OPERATING LIMITS REPORT CYCLE 6
/
/0/3[97 Prepared by:
Opt..
Sv B. L. Mye[s/ '
8 Date Principal Engineer - Nuclear Fuel Reviewed by:
~
7 * *'f7 G. A. Rubley Date Senior Engineer - Nuclear Fuel to/rl97 J. M. Thdrson Date Supervisor - Reactor Engineering
.] TW 10 7-97 L. T. Frasson Date COLR Check. list Reviewer Approved by:
/$ch WW[b
/0 - 8 'f 7 S. T-C Hsieh V
Date Supervisor - Nuclear Fuel OCTOBER 1997
7 COLR - 6 Revision 1 Page 2 of 16 TABLE OF CONTENTS
1.0 INTRODUCTION
AND
SUMMARY
.............................. 4 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE............... 5 2.1 De finition........................................... 5 2.2
. Determinatica of MAPLHGR Limit.......................... 5 2.2.1 Calculation of MAPFAC(P)........................... 7 2.2.2 Calculation of MAPFAC(F)........................... 8 3.0 MINIMUM CRITICAL POWER RATIO............................. 9 3.1 De finiti on........................................... 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 Determination of LHGR Limit.............................
13 5.0 CONTROL ROD BLOCK INSTRUMENTATION......................
14 5.1 Definition...........
14
6.0 REFERENCES
15 9
CQLR - 6 Revision 1 Page 3 of 16 LIST OF TABLES TABLE 1 FUEL TYPE-DEPENDENT STANDARD MAPLHGR LIMITS 6
TABLE 2 FLOW-DEPENDENT MAPLHGR LIMIT COEFFICIENTS.......... 8 l_
TABLE 3 OLMCPRoo3 AS A FUNCTION OF EXPOSURE AND T.........
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 FILTER 14
\\
)
COLR 6 Revision 1 Pcge 4 of 16 i
1.0 INTRODUCTION
AND SUhlhlARY This report provides the cycle specific plant operating limits, which are listed below, for Fermi 2, Cycle 6, as required by Technical Specifications 6.9.3. The analytical methods used to determine these core operatin g limits are those previously reviewed and approved by the Nuclear Regulatory Commission in G'dSTAR II.3 A' The cycle specific limits contained within this report are valid for the full range of the licensed operating domain.63 Revision 1 of this report has been written for two reasons. First, Section 5.2, RBM Applicability, which was added to COLR for the first time in Cycle 6, has been deleted since it is now redundant to the Technical Specifications as changed by Amendment 112 " to the Fermi-2 Facility Operating Licerise. Secondly, the core loading pattern has been changed from that which was assumed in the original reload licensing work for Cycle 6 due to the replacement of failed fuel bundles YJ7119 and YJ2802 with bundles LYX690 at:d LYX742 respectively (with the additional swap of bur.dle YJ7145 to the previous core ir,atian of bundle YJ7119 and bundle YJ2787 to the previous core location of bundle YJ280'j.
These fuel moves meet the criteria in 'section 3.4.2 of GESTAR 11 ' for acceptable deviations from the reference core design without adversely affecting the licensing analysis. Additionally, GE has s
m ai. n. 22 performed sufficient analyses to confirm that the original Cycle 6 reload licensing work is still applicable and bounding to the revised core loading. As a result, none of the operating limits contained in COLR 6 Rev. O have been changed in Rev.1.
2 OPERATING LINIIT TECIINICAL SPECIFICATION APL11GR 3/4.2.1 MCPR 3/4.2.3 LIIGR 3/4.2.4 RBM 3/4.3.6
& 3/4.1.4.3 APL11GR a AVERAGE PLANAR LINEAR 11 EAT GENERATION RATE MCPR
= MINIMUM CRITICAL POWER RATIO LIIGR
= LINEAR IIEAT GENERATION RATE RBM
= ROD BLOCK MONITOR SETPOINTS l
cot.R 6 Revision 1 Page 5 of 16 2.0 AVERAGE PLANAR LINEAR IIEAT GENERATION RATE TECll SPEC IDENT OPERATING LIMIT 3/4.2.1 APLilGk 2.1 Definition The AVERAGE PLANAR LINEAR IIEAT GENERATION RATE (APLIIGR) shall be applicable to a specific planar height and is equal to averaging the LINEAR IIEAT GENERATION RATE over each fuel rod in the plane.
2.2 Determination of MAPLIIGR Limit The maximum APLilGR (MAPLilGR) limit is a function of reactor power, 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 criteria will not be violated dar'.ng any postulated transient events. The MAPLIIGR limit ensures that the peak clad temperature during a LOCA will not exceed the limits as specified in 10CFR5u.46(b)(1) and that the fuel design analysis criteria defined in References 1 and 2 will be met.
Th-MAPLIIGR limit is calculated by the following equation:
AMPUlGRg AflN( AMPulGR (P). AMPUlGR (in) where:
AMPulGR (P). AMPHC (P) x AMPLHGR, AMPUlGR (F). AMPMC (F) x AMPUlGR, MAPLilGRno, the standard MAPLilGR 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. 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, MAPLilGRsro hall be determined by s
interpolation from Table 1.
in,t
COLR.6 Revision !
Pcp 6 of 16 MAPFAC(P), the core power-dependent MAPLIIGR limit adjustment factor, shall be calculated by using Section 2.2.1.
MAPFAC(F), the core flow-dependent MAPLilGR limit adjustment factor, shall be calculated by using Section 2.2.2.
TABLE 1 FUEL TYPE-DEPENDENT STANDARD MAPLilGR LIMITS Standard MAPLilGR Limit (KW/FT)
Exposure Fuel Type own'sT 1
2 6
2 2
10 11 u
u 0.0 10.82 10.84 11.73 11.51 11.73 10.75 11.73 0.2 12.00 11.90 10 90 10 92 11.79 l1.54 11,79 10.79 11,79 1.0 12.10 12.00 11.10 11.11 11.90 11.62 11.90 10.90 11.90 2.0 11.36 11.38 12.01 11.71 12.01 11.11 12.01 3.0 11.64 11.66 12.10 11.79 12.10 11.36 12,10 4.0 ll.N 11.88 12.20 11.87 12.20 11.54 12.20 5.0 12.70 12.10 12.17 12.02 12.30 11.%
12.30 11.6
12.30 6.0 12.30 12.18 12.40 12.04 12.40 11.81 12.40 1.0 12.48 12.38 12.51 12.13 12.51 11.95 12.51 8.0 12.68 12.61 12.62 12.23 12 62 12.09 12.6" 9.0 12.88 12.84 12.68 12.34 12.68 12.23 12.63 10.0 12.80 12.20 13.04 13.02 12.70 12.48 12.70 12.39 12.70 12.5 13.07 13.07 12.57 12.50 12.57 12.46 12.57 15.0 12.90 12.20 12.83 12.83 12.17 12.19 12.17 12.18 12.17 17.5 l1.78 11,82 Il.78 11.88 11.78 20.0 12.70 12.10 12.18 12.18 11.39 11.45 11.39 11.57 11.39 D
25.0 11.70 11.60 11.54
!!.54 10.63 10.71 10 63 10.88 10.63 30.0 10.80 11.20 9.91 9.99 9.91 10.15 9.91 35.0 10.26 10.26 9.24 9.28 9.24 9.43 9.24 40_0 9.00 9.30 8.62 8.59 8.62 8.73 8.62 45.0 8.76 8.72 8.03 7.91 8.03 8.05 8.03 50.0 7.45 7.24 7.45 7.37 7.45 50.60 5.88 50.80 5.88
$5.0 6.84 6.56 6.84 6.68 6.84 t
Fuel Types I = P8CIB176-4GZ-100M 150 T 10 = G611-P9 CUB 35310GZ-100M 146-T 2 = P8CIB219-4GZ 100M 150-T 11 = Gell-P9 CUB 331 llGZ 100M 146-T 6 = GE9B-P8CWB3?l-9GZ-80M 150-T 12 = Gell-P9 CUB 366-15GZ-100T-146-T 7 = GE9B P8CWB32110GZ-80M-150-T 13 = Gell P9 CUB 33111GZ-100M-146-T 9 = Gell P9 CUB 331 ilGZ 100M 146-T
COLR.6 Reviskm 1 Page 7 of 16 2.2.1 Calculation of "APFAC(P)
The $ ore power-dependent MAPLilGR limit adjustment factor. MAPFAC(P), shall be calculated by one of the tollowing equations:
For 0 s P < 25 :
No thermal limits monitoring is required.
For 25 s P < 30 :
With turbine bypass OPERABLE, For core now s 50 Mlbs/hr, AIA?FA C (P). 0.606 0.003R (P 30)
For core now > 50 Mlbs/hr, AfAPFAC (P). 0.586 0.0038 (P-30)
With turbine bynncc INOPERABLE, For core now s 50 M!bs/hr.
AfAPFAC (P). 0.490 0.0050 (P.30)
For core now > 50 Mlbs/hr, A(APFAC (P). 0.438 0.0050 (P-30)
For 30 s P s 100 :
AfAPFAC (P). 1.0 0.005224 (P.100) where:
P = Core power (fraction of rated power times 100).
o
_ _ _ _.. _ _. _ _ _ _ _ _. _.. _.. _ _. ~. _.. _. _ _ _ _. _ __._.___.____.
COLR 6 Revision 1 Page 8 of 16 2.2.2 Calculation of MAPFAC(F)
The core flow-dwendent MAPI.!!GR limit adjustment factor, MAPFAC(F). shall be calculated by tne following equation:
AL4PFAC (F) MIN (l.0, A, u H T, g,y 100 where:
WT = Core flow (Mlbs/hr).
Ap = Given in Table 2.
i B, = Given in Table 2.
i
)
TABLE 2 FLOW-DEPENDENT MAPLilGR LIMIT COEFFICIENTS Maximum Core Flow
- i (Mlbs/hr)
A, B,
110 0.6800 0.4340
'As limited by the Recirculation System MG Set mechanical scoop tube stop setting.
i 4
1 3
COLR. 6 Revision 1 Page 9 of 16 3.0 h11NIh1UM CRITICAL POWER RATIO TECil SPEC IDENT OPERATING LIMIT 3/4.2.3 hiCPR 3,1 Definition The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in the assembly which is cabulated by application of an NRC approved critical power correlation to cause some point in the assembly :o experience boilir.g 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 Limit MCPR of 1.09 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 limitmg 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 t.
t is a measure of scram speed, and is deOned in Technical Specification Section 3/4.2.3.
The OLMCPR shall be calculated by the following equation:
t OLhfCPR. AfAX (AfCPR (P), AfCPR (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 0.02, but OLMCPR does not change.
COLR. 6 Revision 1 l
Page 10 of 16 3.3 Calculation of MCPR(P) 6 MCPR(P), the core power-dependent MCPR operating limit, shall tv calculated by the following equation:
AfCPk (P)
K, u OLhfCPR,.
OLMCPRimfim hall be determined by interpolation from Table 3, and t shall be calculated by s
using Technical Specification Section 3/4.2.3.
Kp, the core power 4ependent MCPR Operating Limit adjustment factor, shall be calculated by using Section 3.3.1.
TABLE 3 OLMCPR,i, AS A FUNCTION OF EXPOSURE AND T i
EXPOSURE CONDITION (MWD /ST)
.in*
i Iloth Turbine Bypass and Moisture Separator Reheater OPERABLE BOC to 8500 t=0 1.28 t=1 1.33 8500 to EOC t=0 1,32 t=1 1.40 Either Turbine Bypass or Moisture Separator Reheater INOPERABLE BOC to EOC t=0 1.36 t=1 1.44 Both Turbine Bypass and Moisture Separator Reheater INOPERABLE BOC to EOC t=0 1.39 t=1 1.47
- The OLMCPR values reported here are for Gell fuel and bound the GE6 and GE9B fuel types.
I
_--mm_.__.__
COLR 6 Revision 1 Page 11 of 16 3.3.1 Calculation of Kr The core power-d: pendent MCPR operating limit adjustment factor. Kr. shall be calculated by using one of t e tollowing equations:
h 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))) x (1.09/1.07)
OLMCPR,,,
where:
Kny, = 1.90 for core flow s S0 Mlbs/hr
= 2.23 for core flow > 50 Mlbs/hr When turbine bypass is INOPERABLE, (K,,,. (0.054 x (30-P))) x (1.09/1.07)
OLMcPR,,,
where:
Kay, = 2.26 for core flow s 50 Mlbs/hr
= 3.03 for core flow > $0 M!bs/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).
g.
COLR 6 Revision 1 Page 12 of 16 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 WT < 40 :
AICPR (F). (1.09/l.07) x (A,x NT, B,) x (1.0 0.0032 x (40. HT))
For WT 2 40 :
AtcPR(F). (1.09/1.07) x AIAX(1.20, (A,x "7. B,))
where:
WT = Core flow (Mlbs/hr).
Ap Given in Table 4.
=
By Given in Table 4.
=
TABLE 4 FLOW-DEPENDENT MCPR LIMIT COEFFICIENTS Maximum Core Flow *
(Mlbs/hr)
Ap B,
110
-0.600 1.731
'As limited by the Recirculation System MG Set mechanical scoop tube stop setting.
COLR 6 Revision 1 Page 13 of 16 4.0 LINEAR IIEAT GENERATION RATE TECil SPEC IDENT OPERATING LlhilT 3/4.2.4 LilGR 4.1 Definitlan The LINEAR IIEAT 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 LIIGR Limit The thermal expansion rates of U0 pellets and Zircaloy cladding are different in that, during 2
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 MAPLilGR 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 LIIGR LIMIT P8CIB1'[64GZ-100M-150-T 13.4 KW/FT P8CIB219-4GZ-100M-150-T 13.4 KW/FT GE9B-P8CWB321-9GZ-80M-150-T 14.4 KW/FF GE9B-P8CWB321-10GZ-80M-150-T 14.4 KW/FT GE11 P9 CUB 331-11GZ-100M-146-T 14.4 KW/FT GE11-P9 CUB 353-10GZ-100M-146-T 14.4 KW/FT GE11-P9 CUB 366-15GZ-100T-146-T 14.4 KW/FT
COLR 6 Revision 1 Page 14 of 16 5.0 CONTROL ROD BLOCK INSTRUMENTATION 4
TECII SPEC IDENT SETPOINT 3/4.3.6 RBM
& 3/4.1.4.3 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 Rod Block Iechnical Epecification improvement Program (ARTS) and the MCPR operating limits.
TABLE 6 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS WITil 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 5.2 Ikleted
a COLR - 6 Revision 1 Pcge 15 of 16 i
6.0 REFERENCES
1.
" General Electric Standard Application for Reactor Fuel (GESTAR 11),* NEDE-24011 P-A, Revision 13 2.
"The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident - SAFER /GESTR Application hiethodology," NEDE 23785-1-PA, Revision 1, October 1984 3.
Fermi 2 SAFER /GESTR-LOCA, Loss-of-Coolant Acc' dent Analysis,"
NEDC-31982P, July 1991, and Errata and Addenda No.1, April 1992 4.
" Lattice-Dependent MAPLIIGR Report for Fermi Power Plant Unit 2 Reload 5 Cycle 6," GE Nuclear Energy, J11-02923hiAPL, Revision 0, November 1996 5.
" Supplemental Reload Licensing Report for Fermi Power Plant Unit 2 Reload 5, Cycle 6," GE Nuclear Energy, J11-02923SRLR, Revision 0, November 1996 6.
letter from T. G. Colburn to W. S. Orser, " Fermi Amendment No. 87 to Facility Operating License No. NPF-43 (TAC NO. h182102)," September 9,1992 7.
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 8.
" Maximum Extended Operating Domain Analysis for Detroit Edison Company Enrico Fermi Energy Center Unit 2," GE Nuclear Energy, NEDC-31843P, July 1990 9.
letter from R. J. Iloward to M. K. Deora and 11. L. Ilubeny, " Operating Flow Dependent MCPR and MAPLHGR Thermal Limits," TDEC-PE-134, September 30,1990 10.
" Power Range Neutron Monitoring System," J. L. Leong, DC-4608, Vol. IX DCD, Rev. O, September 29,1992 and DC-4608 Vol. I Rev. D 11.
Letter from B. R. Fischer to B. L. Myers, " Fermi-2, Cycle 6 Replacement of Leaker Bundle YJ2624," LB#262-96-167, October 14,1996 12.
Letter from R. J. Bragg to B. L. Myers, " Fermi-2 Cycle 6 Rod Withdrawal Error Analysis," RJB:96-27, November 1,1996 13.
Letter from R. J. Bragg to B. L. Myers, " ARTS Multipliers Update for Fermi 2 Cycle 6," RJB:96-29, November 1,1996 14.
Letter from C. J. Papandrea to Dr. Simon lisieh, " Fermi 2 Cycle 6 Safety Limit MCPR Results," CJP2:96-163, August 23,1996
COLR 6 Revision 1 Page 16 of 16
6.0 REFERENCES
(cont'd.)
15.
Letter from R. J. Bragg to B. L. Myers, " Fermi-2 Cycle SLMCPR Licensing Clarification," RJB:96 22, Rev.1 October 28,1996 i
16.
Ietter from B. R. Fischer to B. L. Myers, " Fermi 2 Cycle 6 St.MCPR Licensing i
Clarification - GE Proprietary Information," LB#262-96-159, October 8,1996 l
17.
12tter from R. J. Bragg to B. L. Myers, " Detroit Edison Questions Regarding the Fermi-2, Cycle 6 Reload Licensing Report," RJB:96-34, November 5,1996 18.
12tter from Andrew J. Kugler (USNRC) to Douglas R. Gipson (Detroit Edison),
" Fermi Issuance of Amendment RE: Cycle-Specific Safety Limit Minimum Critical j
Power Ratios for Cycle 6 (TAC NO. M%373), dated November 5,1996 19.
Ietter from Andrew J. Kugler (USNRC) to Douglas R. Gipson (Detroit Edison),
" Fermi 2 issuance of Amendment RE: Rod Block Monitor Applicability (TAC NO.
I M97338), dated May 15,1997 i
20.
Lette.r frem R. H. Szilard to B. L. Myers, " Fermi 2 Mid-cycle Rod Withdrawal Error (RWE) Analysis Results - GE Proprietary Information," LB#124-97 2, September 19, 1997 i.
21.
Mid-Cycle Startup Report for Post-Power Suppression Operation for Fermi-2 Cycle 6,
[
R. H. Szilard, GE Nuclear Energy, J11-03011 Volume 8. October 1997 i
22.
Ietter from R. H. Szilard to B. L. Myers, " Fermi 2 Cycle 6 Replacement of leaker Bundle VJ7119 Safety Anal sis - GE Proprietary Information," LB#125-97-2, l
September 22,1997 i
23.
12tter from R. H._ Szilard to B. L. Myers, " Fermi 2 Cycle 6 Replacement of 12aker
[
Bundle YJ2802 Safety Analysis - GE Proprietary Information," LB#136-97-2, i
October 3,1997 -
e
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