ML20055G705
| ML20055G705 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/19/1990 |
| From: | Morrissey K YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20055G704 | List: |
| References | |
| NUDOCS 9007240087 | |
| Download: ML20055G705 (10) | |
Text
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I Yankee Cycle 21 I
Core Operating Limits Report Revision 0 I
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Controlled Copy No. _
WPP40/3 9007240087 900719 FDR ADOCK 05000029 I.
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(Wh 30 Propared By:
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Approved By:
Mddt ti, $ _
I Manager (Da e)
. Cacci etor Phy cs Group kO Approved By:
. '(Da(e)
R. K. Sundaram, Manager Loss-of-Coolant Accident Analysis Group I
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Approved byI
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P. A. Bergero anager
' (Date)
I Transient Anal sis Group h 40 S u/c, 7//7/9e Am Approved By:
B. C. Slifer, Director (Da'te )
Nuclear Engineering Department I
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Yankee Atomic E1 metric Company Nuclear Services Division 580 Main Street Bolton, Massachusetts 01740 WPP40/3 I
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l TABLE OF CONTENTS 1
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.P.111 IV LIST OF TICURES........
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1.0 INTRODUCTION
2 2.0 CORE OPERATING LIMITS............................................
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l 1.15T OP TICURES l
Number Title
.Iage l
'1 Power Dependent Insertion Limit 3
2 Peak Linear }! eat Generation Rate 4
j 3
Xenon Redistribution Multiplier 5
4 Reduced Power Multiplier 6
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1.0 INTRODUCTION
This report provides the cycle-specific limits for operation of the Yankee Nuclear Power Station through Cycle 21.
It includes the limits for control rod insertion and reactor power.
In this report, Cycle 21 will frequently be referred to as the Present Cycle.
If any of these limits are exceeded, the action will be taken as defined in the Technical Specifications.
This report has been prepared in accordance with the requirements of Technical Specification 6.9.4.
The core operating limits have been developed i
using the NRC-approved methodologies listed in Technical Specification 6.9.4.
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2.0 CORE OPERATING LIMITS These Present Cycle operating limits have been defined using NRC-approved methodologies. The Present Cycle must be operated within the bounds of these limits and all others specified in the Technical Specifications.
2.1 Power Dependent Insertion Limit (PDIL)
Figure 1 provides the PD1L. The PDIL is based on the requirements of the steam line break transient analysis and is also an important consideration in the analysis of the loss of coolant flow and boron dilution transients, since it limits the minimum shutdown margin available.
i 2.2 Peak Linear Heat Generation Rate (LHGR)
Figure 2 provides the allowable peak rod LHGR.
Limiting the peak LHGR I
during Condition I events provides assurance that the initial conditions assumed for the LOCA analyses are met and the ECCS acceptance criteria limits of 10CFR50.46 are not exceeded.
2.3 Xenon Redistribution Multiplier Figure 3 provides the xenon redistribution multiplier.
The xenon multiplier was selected to conservatively account for the effect of xenon redistribution transients on LHGR which can result from control rod motion at full power.
2.4 Reduced Power Multiplier Figure 4 provides the reduced power multiplier.
This multiplier was selected to prevent exceeding the allowable LHGR limits within the first few hours following return to power after control rod insertion outside the operating band for 100% allowable power as provided in Figure 1.
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FIGURE 1 POWER DEPENDENT INSERTION LIMIT TECHNICAL SPECIFICATION 3.1.3.5 100-c-
90 i UNACCEPTABLE OPERATION
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ci 40-h ACCEPTABLE OPERATION j
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20 -
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0 10 20 30 40 50 60 70 80 90 1
CONTROL ROD GROUP O POSITION (INCHES WITHDRAWN) l l
- ALLOWABLE THERMAL POWER BASED ON THE MAIN COOLANT PUMP COMBINATION IN OPERATION I
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FIGURE 2 ALLOWABLE PEAK ROD LHGR VERSUS CYCLE BURNUP TECHNICAL SPECIFICATION 3.2.1/4.2.1.1 12 I
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9 10 11 12 13 14 15 16 17 18 CYCLE BURNUP (GWD/MTU)
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FIGURE 3 j
MULTIPLIER FOR XENON REDISTRIBUTION VERSUG C'/01 '. BURNUP TECHNICAL SPECIFICATION 4.2.1.2 1.1 I
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'W-MULTIPLIER FOR REDUCED POWER VERSUS CYCLE BURNUP l
TECHNICAL SPECIFICATION 4.2.1.2 I
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10 11 12 13 14 15 16 17 18 CYCLE BURNUP (GWD/MTU)
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