2CAN090902, Cycle 21 COLR

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Cycle 21 COLR
ML092570647
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 09/14/2009
From: David Bice
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2CAN090902
Download: ML092570647 (15)
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Text

Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4710 David B. Bice Acting Manager, Licensing Arkansas Nuclear One 2CAN090902 September 14, 2009 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555-0001

SUBJECT:

ANO-2 Cycle 21 COLR Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6

Dear Sir or Madam:

Arkansas Nuclear One - Unit 2 (ANO-2) Technical Specification 6.6.5 requires the submittal of the Core Operating Limits Report (COLR) for each reload cycle. Attached is Revision 0 of the ANO-2 Cycle 21 COLR. This completes the reporting requirement for the referenced specification.

This submittal contains no commitments.

If you have any questions or require additional information, please contact David Bice at 479-858-5338.

Sincerely, DBB/dbb

Attachment:

ANO-2 Cycle 21 Core Operating Limits Report (COLR)

2CAN090902 Page 2 of 2 cc: Mr. Elmo Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8 B1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205

Attachment To 2CAN090902 ANO-2 CYCLE 21 CORE OPERATING LIMITS REPORT (COLR)

ANO2-NE-09-00002 Revision 0 ENTERGY OPERATIONS ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 21 1

ANO2-NE-09-00002 Revision 0 CORE OPERATING LIMITS REPORT FOR CYCLE 21 INDEX PAGE I. INTRODUCTION ........................................................................................................ 3 II.

SUMMARY

OF CHANGES......................................................................................... 3 III. AFFECTED TECHNICAL SPECIFICATIONS ............................................................ 3 IV. APPROVED METHODOLOGIES USED TO DETERMINE LIMITS ........................... 4 V. CORE OPERATING LIMITS....................................................................................... 6 VI. LIST OF FIGURES ..................................................................................................... 7 2

ANO2-NE-09-00002 Revision 0 ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 21 I. INTRODUCTION This CORE OPERATING LIMITS REPORT (COLR) has been prepared in accordance with the requirements of Arkansas Nuclear One - Unit 2 (ANO-2) Technical Specification 6.6.5 for ANO-2's Cycle 21. This is Revision 0 of the Cycle 21 COLR.

II.

SUMMARY

OF CHANGES Listed below are the changes to the COLR from the latest revision of the Cycle 20 COLR.

  • In Section V. Core Operating Limits, Item 3, a change to the wording for the Moderator Temperature Coefficient (MTC) was required for the Cycle 21-specific MTC vs. burnup breakpoints assumed in the PAC. Specifically the burnup breakpoint of 400.0 EFPD was changed to 380.0 EFPD.
  • Figures 4 and 5, DNBR Margin Operating Limit Based on Core Protection Calculators, Minimum 1 CEAC Operable and Both CEACs Inoperable, respectively, were revised to account for additional ROPM required for the seized rotor event at HFP for ANO-2 Cycle 21.

III. AFFECTED TECHNICAL SPECIFICATIONS

1) 3.1.1.1 Shutdown Margin - Tavg > 200°F
2) 3.1.1.2 Shutdown Margin - Tavg 200°F
3) 3.1.1.4 Moderator Temperature Coefficient
4) 3.1.3.1 CEA Position
5) 3.1.3.6 Regulating and Group P CEA Insertion Limits
6) 3.2.1 Linear Heat Rate
7) 3.2.3 Azimuthal Power Tilt - Tq
8) 3.2.4 DNBR Margin
9) 3.2.7 Axial Shape Index 3

ANO2-NE-09-00002 Revision 0 IV. APPROVED METHODOLOGIES USED TO DETERMINE LIMITS Provided below are the analytical methods used to determine the core operating limits addressed by the individual Technical Specifications. These methods have been reviewed and approved by the NRC.

1) Qualification of the PHOENIX-P / ANC Nuclear Design System for Pressurized Water Reactor Cores, (WCAP-11596-P-A), June 1988, ANC: A Westinghouse Advanced Nodal Computer Code (WCAP-10965-P-A), September 1986, and ANC: A Westinghouse Advanced Nodal Computer Code: Enhancements to ANC Rod Power Recovery (WCAP-10965-P-A, Addendum 1), April 1989 (Methodology for Specification 3.1.1.1, 3.1.1.2, 3.1.1.4, 3.1.3.6; and 3.2.4.b)
2) CE Method for Control Element Assembly Ejection Analysis, CENPD-0190-A, January 1976 (Methodology for Specification 3.1.3.6 and 3.2.3)
3) Modified Statistical Combination of Uncertainties, CEN-356(V)-P-A, Revision 01-P-A, May 1988 (Methodology for 3.2.4.c, 3.2.4.d and 3.2.7)
4) Calculative Methods for the CE Large Break LOCA Evaluation Model, CENPD-132-P, August 1974 (Methodology for 3.1.1.4, 3.2.1, 3.2.3 and 3.2.7)
5) Calculational Methods for the CE Large Break LOCA Evaluation Model, CENPD-132-P, Supplement 1, February 1975 (Methodology for 3.1.1.4, 3.2.1; 3.2.3 and 3.2.7)
6) Calculational Methods for the CE Large Break LOCA Evaluation Model, CENPD-132-P, Supplement 2-P, July 1975 (Methodology for 3.1.1.4, 3.2.1, 3.2.3 and 3.2.7)
7) Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysis of CE and W Designed NSSS, CEN-132, Supplement 3-P-A, June 1985 (Methodology for 3.1.1.4, 3.2.1; 3.2.3 and 3.2.7)
8) Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model, CENPD-132-P, Supplement 4-P-A, Revision 1, December 2000 (Methodology for 3.1.1.4, 3.2.1; 3.2.3 and 3.2.7)
9) Calculative Methods for the CE Small Break LOCA Evaluation Model, CENPD-137-P, August 1974 (Methodology for 3.1.1.4, 3.2.1, 3.2.3, and 3.2.7)
10) Calculative Methods for the CE Small Break LOCA Evaluation Model, CENPD-137, Supplement 1-P, January 1977 (Methodology for 3.1.1.4, 3.2.1, 3.2.3, and 3.2.7)
11) Calculative Methods for the CE Small Break LOCA Evaluation Model, CENPD-137, Supplement 2-P-A, April 1998 (Methodology for 3.1.1.4, 3.2.1, 3.2.3, and 3.2.7)
12) CESEC-Digital Simulation of a Combustion Engineering Nuclear Steam Supply System, December 1981 (Methodology for 3.1.1.1, 3.1.1.2, 3.1.1.4, 3.1.3.1, 3.1.3.6, and 3.2.4.b)
13) Technical Manual for the CENTS Code, CENPD 282-P-A, February 1991 (Methodology for 3.1.1.1, 3.1.1.2, 3.1.1.4, 3.1.3.1, 3.1.3.6, 3.2.4.b) 4

ANO2-NE-09-00002 Revision 0

14) Implementation of ZIRLO Material Cladding in CE Nuclear Power Fuel Assembly Designs, CENPD-404-P-A, November 2001 (Modifies CENPD-132-P and CENPD-137-P as methodology for 3.1.1.4, 3.2.1, 3.2.3, and 3.2.7)
15) Qualification of the Two-Dimensional Transport Code PARAGON, WCAP-16045-P-A, August 2004 (May be used as a replacement for the PHOENIX-P lattice code as methodology for 3.1.1.1, 3.1.1.2, 3.1.1.4, 3.1.3.6, and 3.2.4.b)
16) Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs, WCAP-16072-P-A, August 2004 (Methodology for 3.1.1.4, 3.2.1, 3.2.3, and 3.2.7)
17) Letter: O.D. Parr (NRC) to F.M. Stern (CE) dated June 13, 1975 (NRC Staff Review of Combustion Engineering ECCS Evaluation Model). NRC approval for items 4, 5 and 9 methodologies
18) Letter: O. D. Parr (NRC) to A.E. Scherer (CE), dated December 9, 1975 (NRC Staff Review of the Proposed Combustion Engineering ECCS Evaluation Model changes). NRC approval for item 6 methodology
19) Letter: K.Kniel (NRC) to A. E. Scherer (CE), dated September 27, 1977 (Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for item 10 methodology
20) Letter: 2CNA038403, dated March 20, 1984, J.R. Miller (NRC) to J.M. Griffin (AP&L),

CESEC Code Verification. NRC approval for item 12 methodology

21) CE 16 x 16 Next Generation Fuel Core Reference Report, WCAP-16500-P and Final Safety Evaluation for Westinghouse Electric Company (Westinghouse) Topical Report (TR)

WCAP-16500-P, Revision 0, CE [Combustion Engineering] 16 x 16 Next Generation

[(NGF)] Core Reference Report, (Methodology for Specification 3.1.1.4 Moderator Temperature Coefficient (MTC), 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin, and 3.2.7 for ASI)

22) Optimized ZIRLOTM, WCAP-12610-P-A and CENPD-404-P-A Addendum 1-A, (Methodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Tilt, and 3.2.7 for ASI)
23) Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Supported Mixing Vanes, WCAP-16523-P and Final Safety Evaluation for Westinghouse Electric Company (Westinghouse) Topical Report (TR), WCAP-16523-P, Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Supported Mixing Vanes, (Methodology for 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin and 3.2.7 for ASI)
24) ABB Critical Heat Flux Correlations for PWR Fuel, CENPD-387-P-A (Methodology for Specifications 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin and 3.2.7 for ASI) 5

ANO2-NE-09-00002 Revision 0

25) Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model -

Improvement to 1999 Large Break LOCA EM Steam Cooling Model for Less Than 1 in/sec Core Reflood, CENPD-132, Supplement 4-P-A, Addendum 1-P and Final Safety Evaluation for Westinghouse Electric Company (Westinghouse) Topical Report (TR)

CENPD-132, Supplement 4-P-A, Addendum 1-P, Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model - Improvement to 1999 Large Break LOCA EM Steam Cooling Model for Less Than 1 in/sec Core Reflood, (Methodology for Specification 3.1.1.4 Moderator Temperature Coefficient (MTC), 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI)

V. 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 5.0 % k/k in Modes 1, 2, 3, and 4.
2) 3/4.1.1.2 - SHUTDOWN MARGIN - Tavg 200°F The SHUTDOWN MARGIN shall be greater than or equal to 5.0% k/k in Mode 5.
3) 3.1.1.4 - MODERATOR TEMPERATURE COEFFICIENT The Moderator Temperature Coefficient (MTC) shall be in accordance with Figure 1. The Beginning of Cycle (BOC) positive COLR MTC limit line of Figure 1 is from BOC to 140.0 EFPD. From 380.0 EFPD to End of Cycle (EOC) the positive COLR MTC limit line is linear from an MTC of 0.0 E-4 k/k/°F at 0% power to an MTC of -1.0 E-4 k/k/°F at 100% power, which is bounded by the BOC positive MTC limit. Between 140.0 EFPD and 380.0 EFPD the positive MTC limit may be interpolated linearly with burnup.
4) 3.1.3.1 - CEA POSITION With one or more CEAs trippable but misaligned from any other CEAs in its group by more than the Technical Specification 3.1.3.1 allowed value, the minimum required core power reduction for Modes 1 and 2 is specified in Figure 2.
5) 3.1.3.6 - REGULATING CEA INSERTION LIMITS The regulating CEA groups and Group P shall be limited to the withdrawal and insertion limits shown on Figure 3. Figure 3 assumes that Groups 1 through 5 are maintained at or above the Programmed Insertion Limit.
6) 3/4.2.1 - LINEAR HEAT RATE With COLSS out of service, the linear heat rate shall be maintained 13.7 kW/ft.

6

ANO2-NE-09-00002 Revision 0

7) 3.2.3 - AZIMUTHAL POWER TILT- Tq The measured AZIMUTHAL POWER TILT shall be maintained 0.03.
8) 3/4.2.4 - DNBR MARGIN The DNBR limit shall be maintained by one of the following methods:

a) With COLSS in service and neither CEAC operable - Maintain COLSS calculated core power less than or equal to COLSS calculated core power operating limit based on DNBR decreased by 10%.

b) With COLSS out of service and at least one CEAC operable - Operate within the Region of Acceptable Operation shown on Figure 4, using any operable CPC channel.

c) With COLSS out of service and neither CEAC operable - Operate within the Region of Acceptable Operation shown on Figure 5, using any operable CPC channel.

9) 3.2.7 - AXIAL SHAPE INDEX The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:

a) COLSS IN SERVICE

- 0.27 ASI + 0.27 b) COLSS OUT OF SERVICE (CPC)

- 0.20 ASI + 0.18 VI. LIST OF FIGURES Figure 1 Moderator Temperature Coefficient Figure 2 Required Power Reduction After Inward CEA Deviation Figure 3 CEA Insertion Limits Versus Thermal Power Figure 4 DNBR Margin Operating Limit Based on Core Protection Calculators (COLSS Out of Service, CEAC Operable)

Figure 5 DNBR Margin Operating Limit Based on Core Protection Calculators (COLSS Out of Service, Both CEACs Inoperable) 7

ANO2-NE-09-00002 Revision 0 FIGURE 1 Moderator Temperature Coefficient 5.00E-05 (0, 0.50)

Unacceptable Operating Region 0.00E+00 (20, 0.32)

(50, 0.05)

(60, 0.00)

(100, -0.20)

-5.00E-05

-1.00E-04 MTC (Delta K/K/Degree F)

-1.50E-04 Acceptable Operating Region

-2.00E-04

-2.50E-04

-3.00E-04

-3.50E-04

-3.80 E-04 Unacceptable Operating Region

-4.00E-04 0 10 20 30 40 50 60 70 80 90 100 Core Power (% of Rated Thermal Power)

Note:

Per Technical Specification 3.1.1.4.a. and b., the Moderator Temperature Coefficient (MTC) maximum upper design limit shall be less positive than +0.5 x 10-4 k/k/°F whenever THERMAL POWER is 70% of RATED THERMAL POWER and less positive than 0.0 x 10-4 k/k/°F whenever THERMAL POWER is > 70% of RATED THERMAL POWER. Therefore, the actual MTC must be less than the COLR upper limit at zero power. At all other powers, the actual MTC may be equal to the COLR upper limit.

8

ANO2-NE-09-00002 Revision 0 FIGURE 2 REQUIRED POWER REDUCTION AFTER INWARD CEA DEVIATION*

30 (28% @ 120 min.)

25 Minimum Required Power Reduction (% of Rated Power) 20 15 10 5

0 0 15 30 45 60 75 90 105 120 Time After Deviation (minutes)

  • When core power is reduced to 60% of rated power per this limit curve, further reduction is not required 9

ANO2-NE-09-00002 Revision 0 FIGURE 3 CEA INSERTION LIMITS VERSUS THERMAL POWER 150 150 GROUP P PDIL GROUP 6 PDIL 135 135 (74, 135)

Transient Insertion Limit Transient Insertion Limit 120 120 (100, 112.5)

Group P CEA Position, Inches Withdrawn Group 6 CEA Position, Inches Withdrawn (65, 112.5) 105 105 Long Term Long Term 90 Steady State SHUTDOWN 90 Steady State Actions Apply MARGIN NOT Actions Apply SATISFIED 75 75 60 (44, 60) 60 (82.5, 60)

Short Term Steady State Short Term 45 Actions Apply 45 Steady State Actions Apply 30 30 SHUTDOWN SHUTDOWN 15 MARGIN NOT 15 MARGIN NOT SATISFIED SATISFIED (20, 0) (62.5, 0) 0 0 0 10 20 30 40 50 60 70 80 90 100 0 10 20 30 40 50 60 70 80 90 100 Power (%) Power (%)

Note: Regulating Groups 1 through 5 at or above Programmed Insertion Limit 10

ANO2-NE-09-00002 Revision 0 FIGURE 4 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS ANO-2 Cycle Independent COLSS OOS Limit Lines Minimum One CEAC Operable 3.4 3.3 3.2 ACCEPTABLE OPERATION Any Power Level 3.1 3.0 (0.03, 2.91) 2.9 (0.18, 2.91) 2.8 2.7 ACCEPTABLE OPERATION Power at or above 80%

(-0.20, 2.65) 2.6

(-0.07, 2.49) 2.5 (0.18, 2.49)

DNBR 2.4

(-0.20, 2.37)

ACCEPTABLE OPERATION 2.3 Power at or above 90%

2.2 2.1 (-0.10, 2.06)

(0.18, 2.06) 2.0 (-0.20, 2.00) 1.9 UNACCEPTABLE OPERATION Any Power Level 1.8 1.7 1.6

-0.3 -0.2 -0.1 0.0 0.1 0.2 0.3 CPC Indicated ASI NOTE: DNBR greater than that indicated at the top of the figure is acceptable, provided the indicated ASI limits remain between the bounds that are shown for lower DNBR.

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ANO2-NE-09-00002 Revision 0 FIGURE 5 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS ANO-2 Cycle Independent COLSS OOS Limit Both CEACs Inoperable 4.2 4.1 4.0 ACCEPTABLE OPERATION Any Power Level 3.9 3.8 3.7

(-0.01, 3.57)

DNBR 3.6 (0.18, 3.57) 3.5 3.4 3.3

(-0.20, 3.29) UNACCEPTABLE OPERATION Any Power Level 3.2 3.1 3.0

-0.3 -0.2 -0.1 0.0 0.1 0.2 0.3 CPC Indicated ASI NOTE: DNBR greater than that indicated at the top of the figure is acceptable, provided the indicated ASI limits remain between the bounds that are shown for lower DNBR.

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