ML20046A245
| ML20046A245 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/22/1993 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20046A235 | List: |
| References | |
| NUDOCS 9307270139 | |
| Download: ML20046A245 (12) | |
Text
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. ENTERGY OPERATIONS:
ARKANSAS NUCLEAR ONE - UNIT 2
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FOR CYCLE 10 REVISION 0 l
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ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 10, REVISION 0 INDEX P_ AGE I.
INTRODUCTION 3
II.
AFFECTED TECHNICAL SPECIFICATIONS 3
III.
CORE OPERATING LIMITS 4
IV.
METIIODOLOGIES 6
V.
LIST OF FIGURES 7
2
ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 10, REVISION 0 i
1.
INTRODUCTION l
This COIE OPERATING LIMITS REPORT (COLR) has been prepared in accordance with the requirements of Arkansas Nuclear One - Unit 2 (ANO-2) Technical Specification 6.9.5 for ANO-2's Cycle 10. The core operating limits have been developed using the NRC approved methodologies specified in Section IV. This is the initial issuance of the
'l Cycle 10 COLR.
1 II.
AFFECTED TECIINICAL SPECIFICATIONS 1) 3/4.1.1.1 Shutdown Margin - Tavg > 200 F 2) 3/4.1,1.2 Shutdown Margin - Tavg s 200 F 3) 3.1.1.4 Moderator Temperature Coefficient 4) 3.1.3.1 Movable Control Assemblies - CEA Position 5) 3.1.3.6 Regulating CEA Insertion Limits 6) 3 1.3.7 Part Length CEA Insertion Limits 7) 3/4.2.1 Linear Heat Rate 8) 3.2.3 Azimuthal Power Tilt - Tq 9) 3/4.2.4 DNBR Margin 10) 3.2 7 Axial Shape Index 3
lH.
CORE OPERATING LIMITS The cycle-specific operating limits for the specifications listed are presented below.
1) 3/4.1 1.1 - SHUTDOWN MARGIN-T vg > 200 F a
The SHUTDOWN MARGIN shall be greater than or equal to 5.5% Ak/k in Modes 1,2,3, and 4.
2) 3/4.1.12 - SHUTDOWN MARGIN - T s 200 F g
The SIIUTDOWN MARGIN shall be greater than or equal to 5.0% Ak/k in Mode 5.
3) 3.1.1.4 - MODERATOR TEMPERATURE COEFFICIENT The Moderator Temperature Coefficient (MTC) shall be:
a) less positive than + 0.5 E-4 A k/k/ F whenever THERMAL POWER is s 70% of RATED THERMAL POWER L
b) less positive than 0.0 A k/k/ F whenever THERMAL POWER is > 70%
L of RATED THERMAL POWER c) less negative than - 3.4 E-4 A k/k/ F at RATED THERMAL POWER i
4) 3.1.3.1 - MOVABLE CONTROL ASSEMBLIES - CEA POSITION With one or more full length or part length CEAs trippable but misaligned from any other CEAs in its group by more than the Technical Specification 3.1.3.1 L
allowed value, the minimuni required Modes 1 and 2 core power reduction is.
specified in Figure 1.
5) 31.3.6 - REGULATING CEA INSERTION LIMITS The regulating CEA groups shall be limited to t! n withdrawal sequence and to:
the insertion lirnits shown on Figure 2.-
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e 6) 3.13.7 - PAlU LENGTH CEA INSERTION LIMITS The part length CEA group shall be limited to the insenion limits shown on Figure 3.
7) 3/41 LINEAR HEAT RATE With COLSS out of sersice, the linear heat rate shall be maintained s 12.1 kW/ft.
' 8) 3 2.3 - AZIMUTHAL POWER TILT-Tg The measured AZIMUTHAL POWER TILT shall be maintained s 0.10.
9)
- 3/4.2.4 - DNI3R MARGIN The DN13R liiilit shall be maintained by one of the following methods:
a)
With COLSS out of service and at least one CEAC operable - Operate 5
within the Region of Acceptable Operation shown on Figure 4, using any operable CPC channel.
b)
With COLSS out of service an,1 neither CEAC operable - Operate within-the Region of Acceptable Operation shown on Figure 5, using any operable CPC cinnnel.
)
i 10) 3.2.7 - AXIAL SHAPE INDEX i
The core average AXI AL SHAPE INDEX (ASI) shall be maintained within the
)
following limits:
a)
COLSS IN SERVICE
- 0.28 s ASI.< + 0.28
- b)
- 0.20 s ASI s + 0.20 1
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METilODOI.OGIES
- The analytical methods used to determine the core operating limits listed above are those previously reviewed and approved by the NRC in:
1)
"The ROCS and DIT Computer Codes for Nuclear Design," CENPD-266-P-A, April 1983. hiethodology for the limit on Shutdown Margins, MTC, and the Regulating CEA Insertion Limits.
2)
"CE Method for Control Element Assembly Ejection Analysis," CENPD-0190-A, January 1976. Methodology for the Regulating CEA Insertion Limits and Azimuthal Pow er Tilt.
3)
" Statistical Combination of Uncertainties Combination of System Parameter Uncertainties in Thermal Margin Analyses for Arkansas Nuclear One Unit 2" CEN-139(A)-P, November 1980. Methodology for the limits on the DMsR Margin and the ASL 4)
" Calculative Methods for the CE Large Break LOCA Evaluation Model,"
CENPD-132-P, Aup.t 1974. Methodology for the limits on the Linear lleat Rate and Azimuthal Power Tilt.
5)
" Calculational Methods for the CE Large break LOCA Evaluation Model,"
CENPD-132-P, Supplement 1, February 1975. Methodology for the limits on the MTC, Linear Heat Rate, Azimuthal Power Tilt and ASI.
. 6)
" Calculational Methods for the CE Large Break LOCA Evaluation Model,"
CENPD-132-P, Supplemer luly 1975. Methodology for the limits on the MTC, Linear Heat Rate,
. Nal Power Tilt and ASI.
7)
" Calculational Methods for the CE Small Break LOCA Evaluation Model,"
CENPD-137-P, August 1974. Methodology for the limits on the MTC, Linear lleat Rate, Azimuthal Power Tilt and ASI.
8)
"CESEC. Digital Simulation of a Combustion Engineering Nuclear Steam Supply System", December 1981. Methodology for the limits on the Shutdown Margins, MTC, Movable Control Assemblies - CdA Position, Regulating CEA Insertion Limits, Part Length CEA Insertion Limits and Azimuthal Power Tilt.
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LIST OF FIGUltES ~
Figure 1.
Recuired Power Reduction After CEA Deviation i
Figure 2 CEA Insertion Limits Versus Thermal Po'wer :
.l Figure 3.
Part Length CEA Insertion Limit.Versus Thermal Power.
Figure 4 DNBR Margin Operating Limit Based on Core Protection Calculators (COLSS Out of Service, CEAC Operable) l Figure 5 DNBR Margin Ope-ating Limit Based on Core Protection-Calculators (COLSS Out of Service, Both CEACs Inoperable) 4 1
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FIGURE 1 Iti:QUlitED POWER REDUCTION AFTER CEA DEVIATIONa
- When core power is reduced to 60% of rated power per this limit curve, further reduction is not required 30 1
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