ML20028H731
| ML20028H731 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/14/1990 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20028H729 | List: |
| References | |
| NFU-114, NFU-114-R, NFU-114-R00, NUDOCS 9101290269 | |
| Download: ML20028H731 (19) | |
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NFU-114 Revision 0 December 14, 1990 CORE OPERATING LIMITS REPORT HOPE CREEK GENERATING STATION CYCLE 4 / RELOAD 3 December 14, 1990 C
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9101290269 910124 PDR ADOCK 05000354 P
I tiFU-114 Revision 0 December 14, 1990
ABLE OF COliTENTS SECTION TITLE EAGE 1.0 Introduction 4
2.0 Limiting Conditions for Operation 5'
2.1 Maximum Average Planar Linear Heat 6
Generation Rate 2.2 Minimum Critical Power Ratio 12 2.3 Linear Heat Generation Rate 18 3.0 References 19 2
NFU-114 Revision 0 December 14, 1990 LIST OF FIGURES t10MBEB TITLE PAGE 2-1 MAPLHGR Versus Exposure for Fuel Bundle Type 7
P8CIB278 2-2 MAPLHGR Versus Exposure for Fuel Bundle Type B
^
P7CRB299HA 2-3 MAPLHGR Versus Exposure for Fuel Bundle Type 9
P8CRB300L 2-4 MAPLHGR Versus Exposure for the Most Limiting 10 Lattice of Fuel Bundle Type P8CWB325-11GZ1 2-5 MAPLHGR Versus Exposure for the Most Limiting 11 Lattice of Fuel Bundle Type P8CWB325-11GZ2 2-6 MCPR Versus Tau At Rated Flow For Fuel Bundle Type 13 GE9B From BOC To EOC-2000 MWD /ST 2-7 MCPR Versus Tau At Rated Flow For Fuel Bundle Type 14 GE9B From EOC-2000 MWD /ST To EOC 2-8 MCPR Versus Tau At Rated Flow For Fuel Bundle Type 15 GE7B From BOC To EOC-2000 MWD /ST 2-9 MCPR Versus Tau At Rated Flow Fur Fuel Bundle Type 16 GE7B From EOC-2000 MWD /ST To EOC 2-10 K Versus Core Flow 17 g
3
l NFU-114 Revision 0 December 14, 1990
1.0 INTRODUCTION
The purpose of this report is to provide a description of the Core Operating Limits for the Hope Creek Generating Statiors Unit 1 Cycle 4 operation.
This report is intended to be used for operation of the Hope Creek reactor core and for the training of the operations staff with respect to the cycle specific aspects of core operation.
The Hope Creek Technical Specifications references this report as the source for certain LIMITING CONDITIONS FOR OPERATION.
- These are included in section 2 of this document.
This document is specific to Hope Creek Cycle 4 / Reload 3 and shall not be applicable to any other core or cycle design.
4
1 NFU-114 Revision 0 Decetaber 14, 1990 l
L_Q LIMITING CONDITIONS FOR OPERATION The LIMITING CONDITIONS FOR OPERATION presented in this section are referenced by the Hope Creek Technical Specifications.
Tech. Spec Title 3/4.2.1 Average Planar Linear Heat Generation Rate 3/4.2.3 Minirnum Critical Power Ratio 3/4.2.4 Linear Heat Generation Rat.e 5
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NFU-114 Revision 0 December 14, 1990 M
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION: ALL AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) for bundle type P8CIB278, P8CRB299HA, and P8CRB300L as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits shown in Figure 2-1, 2-2, and 2-3 respectively.
The APLHGRs for each lattice type (excluding natural Uranium) in bundle P8CWB325-11GZ1 as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits shown in Figure 2-4. The APLHGRs for each lattice type (excluding natural Uranium) in bundle P8CWB325-11GZ2 as a f?inction of AVERAGE PLANAR EXPOSURE shall not exceed the limits shown in Figure 2-5. The limits of these figures shall be -
- reduced to a value of 0.86 times the two recirculation loop operation limit when in single recirculation loop operation.
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am-ty s-*- e es o a na Fig. 2-1 MAPLHGR Versus Exposure for Fuel Bundle P8CIB278
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4 NFU-114 Revision 0 December 14, 1990 M
MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION: The MINIMUM CRITICAL POWER RATIO (CPR) shall be equal to or greater than the CPR limit times the k, shown in Figure 2-10.
It requires an adjustment to the K values for bundle flows below 0.4 M1b/f t -hr and incorporation of,a 3% adjustment f actor if inlet 2
subcooling exceeds 70 Btu /lbm.
The CPR limit it shown in Figure 2-6, or 2-7, as applicable, for ~
GE9B bundles and in Figure 2-8, or 2-9, as applicable, for GE7B bundles.
The CPR limit is a function of Core Average Exposure, and core average scram speed, I (Tau), defined by Technical Specification 3.2.3.
End-of-Cycle Recirculation Pump Trip system status is defined operable or inoperable per Technical Specification 3.3.4.2.
Main Turbine Bypass must be operable per Technical Specification 3.7.7.
12
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Type GE98 From BOC To EOC-2000 MWD /ST
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l Type GE78 From EOC-2000 MWD /ST To EOC
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- 1FU-ll4 Revision 0 December 14, 1990 1.4 117.0 %.
Automate Fkn' For 40% < F < 100% Kg. MAX (1.00. (A +B(Ft100))
Control (AFC)
For F < 40%
Kg. ((A +8(F/100))((1.00 + 0.0032 (40. F))
112. W.
1.3 107.0 %*
MODE A
B 102.5 %*
AFC 1.u10 0.u1 117.0 1.4035 0.u1 112 0 1.3783 0.41 107.0 1.3528 0.u1 102.5 1.3308 0.41 1.2 Kg 1.1 1.0
- Manual Flow Control Scoop Tube Selpoint Calibretton Postioned Such That These Are Maximum Core Flow Values.
04 3
g g
so 100 CORE FLOW, F (% rWed)
Fig. 2-10 Kf Versus Core Flow 17
NFU-114 Revision 0 December 14, 1990 M
LINEAR HEAT GENERATION RAlf6 LIMITIllG CONDITION FOR OPERATION : The LINEAR HEAT GENERATION RATE (LHGR) for each type of fuel shall not exceed the applicable limits:
E,yel Typ3 LHGR Limit (Kw/ft)
GE7B-P8CIB278 13.4 GE7B-P8CRB299HA 13.4 GE7B-P8CRB300L 13.4 GE9B-P8CWB325-11GZ1 14.4 GE9B-P8CWB325-11GZ2 14.4 i
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NFU-114 Revision 0 December 14, 1990 L_Q REFERENCES 1.
" General Electric Standard Application For Reactor Fuel",
NEDE-24011-P-A, Revision 9, August 1988.
2.
R.B.
Linford, " Analytical Methods of Plant Transient Evaluation for the GE BWR", NEDO-10802, February 1973.
3.
" Qualification of the One Dimensional Core Transient Model for Boiling Water Reactors", NEDO-24154, October 1978.
4.
" Supplemental Reload Licensing Submittal for Hope Creek -
Generating Station Unit 1, Reload 3 Cycle 4", General Electric Company, 23A6526, Rev 0, December, 1990.
5.
A.D.Vaughn (General Electric) to E.S.
Rosenfeld (PSE&G),
"MAPLHGR Limits for Hope Creek Reload 1 Fuel Assemblies",
December 8, 1987, NFUI-87-552.
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