ML20046A245

Rev 0 to Core Operating Limits Rept for Cycle 10.

ML20046A245
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/22/1993
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20046A235	List: ML20046A234 ML20046A240 ML20046A245
References
NUDOCS 9307270139
Download: ML20046A245 (12)

Text

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. ENTERGY OPERATIONS:

ARKANSAS NUCLEAR ONE - UNIT 2  ;

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CORE OPERATING LIMITS REPORT ,

I FOR CYCLE 10 REVISION 0  !

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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

l ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT l 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 l

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 - T q

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- Tavg > 200 F 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 - Tg s 200 F 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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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-T g 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.

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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) COLSS OUT OF SERVICE (CPC)

- 0.20 s ASI s + 0.20 1

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y IV. 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.

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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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i V. 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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